Specific effective activity (Aeff). Determination of specific effective activity of building materials Specific effective activity of natural bitumen radionuclides

GOST 30108-94

INTERSTATE STANDARD

BUILDING MATERIALS AND PRODUCTS

DETERMINATION OF SPECIFIC EFFECTIVE
ACTIVITIES OF NATURAL RADIONUCLIDES

GOSSTROY OF RUSSIA

Foreword

1 DEVELOPED by the NIISF Institute with the participation of VNIPIIstromsyrye Russian Federation INTRODUCED by the Gosstroy of Russia2 ACCEPTED by the Interstate Scientific and Technical Commission for Standardization and Technical Rationing in Construction (MNTKS) on March 14, 1994. Voted for adoption:

Name of the state

Name of the public administration body for construction

The Republic of Azerbaijan Gosstroy of the Azerbaijan Republic
Republic of Armenia State Architecture of the Republic of Armenia
Republic of Belarus Gosstroy of the Republics and Belarus
The Republic of Kazakhstan Ministry of Construction of the Republic of Kazakhstan
Republic of Kyrgyzstan State Construction Committee of the Kyrgyz Republic
The Republic of Moldova Ministry of Architecture of the Republic of Moldova
The Russian Federation Gosstroy of Russia
The Republic of Tajikistan Gosstroy of the Republic of Tajikistan
The Republic of Uzbekistan State Committee for Construction of the Republic of Uzbekistan
3 INTRODUCED FOR THE FIRST TIME4 INTRODUCED 1 January 1995 as state standard Russian Federation Decree of the Gosstroy of Russia dated June 30, 1994 No. 18-48

INTERSTATE STANDARD

BUILDING MATERIALS AND PRODUCTS

Determination of specific effective activity
natural radionuclides

Building materials and elements. Determination of
specific activity of natural radioactive nuclei

Introduction date 1995-01-01

1 AREA OF USE

This standard applies to inorganic bulk building materials (crushed stone, gravel, sand, cement, gypsum, etc.) to building products (facing boards, decorative and other products made of natural stone, brick and wall stones), as well as industrial waste used directly as building materials or as a raw material for their production, and establishes methods for determining the specific effective activity of natural radionuclides for evaluating building materials and products in accordance with the requirements given in Appendix A, and the procedure for monitoring.

2 REGULATORY REFERENCES

This standard uses references to the following standards: GOST 8.326-89 GSI. Metrological certification of measuring instruments. Basic provisionsGOST 8.513-84 GSI. Verification of measuring instruments. Organization and procedure for carrying out GOST 24104-88 Laboratory scales for general purposes and exemplary. General technical conditions and GOST 29329-92 Scales for static weighing. General technical requirements (Revised edition, Rev. No. 1).

3 DEFINITIONS, SYMBOLS AND ABBREVIATIONS

The following terms and designations are used in this standard: Natural radionuclides (NRN) - the main radioactive nuclides of natural origin contained in building materials: radium (226 Ra), thorium (232 Th), potassium (40 K); Specific activity of a radionuclide (A) is the ratio of the activity of a radionuclide in a sample to the mass of the sample, Bq/kg; formula

g de A Ra , А Th , А k - specific activities of radium, thorium, potassium, respectively, Bq/kg.

4 METHODS FOR DETERMINING THE SPECIFIC EFFECTIVE ACTIVITY OF NATURAL RADIONUCLIDES

This standard establishes express and laboratory methods for determining the specific effective activity of NRN in building materials and products. 4.1 Express method 4.1.1 Purpose of the method industrial waste (hereinafter - bulk materials), as well as building products in accordance with the current and regulatory documents; - a preliminary assessment of the developed rocks in a quarry (Appendix D). The condition for using the express method is the absence of contamination of materials and products with technogenic radionuclides. R KP-305MS type), with the following technical characteristics: - the lower limit for determining the value of A eff is not more than 100 Bq / kg; - the relative error in determining the value of A eff is not more than 30%. 4.1 .2.2 Control radionuclide source with activity from 100 to 1000 Bq for checking the reproducibility of radiometer readings. methods and measurements in the established order, providing them with the introduction of the necessary corrections and evaluation of the heating snost and results in conditions of real measurements. 4.1.2.3 (Revision, Rev. No. 1). 4.1.3 The procedure for preparing equipment for measurements and monitoring its performance and Preparation of equipment for measurements is carried out in accordance with the instructions for its operation. To check the operation of the equipment, measurements are taken before and after working measurements using a control source. The difference in readings between this and measurements and should not exceed 5%. 4.1.4 The procedure for conducting control with an interval of no more than 10 m, the height of the lower section from the base of the cone or stack must be at least 1 m; ¾ on the namy wa map - at the nodes of a rectangular set and 10 ´10 m. 4.1.4.2 input control bulk building materials and alo to control points and choose in each vehicle at a distance of at least 1 m from the side wall: - and in railway transport (gondola car and platform) - at least two points; - in road transport - one point in the center of the body; - on the water transport(on a barge - site or bunker ships) - at least two points located along the axis of the vessel. m, and a height of 0.5 m, or choose a pallet (package) of products not laid in a herringbone pattern with dimensions not less than those indicated in the center of the upper plane of the products, select a control point. 4.1.4.4 Measurements are carried out by installing a block detection of the radiometer at the control point on flat surface material. The surface on which the dimensions of protrusions (cavities) do not exceed the diameter of the detection unit is taken as a flat one. At least three consecutive measurements are carried out at each control point. at least 20 m from buildings, structures, rock masses and building materials and products. 4.1.5 Rules for processing results in measurements 4.1.5.1 formula:

(2)

where i = 1, 2, ..., n is the measurement number at the given point; n is the number of measurements at a given point (n ³ 3); A eff. i - the value of the value A eff pr and i-th dimension; D is the absolute measurement error, estimated in accordance with the measurement procedure. 4.1.5.2 eff.t. j obtained during measurements at the control points of a given batch. , binding of control points of measurement, features of measurement conditions (distance from the source of side radiation, air temperature, etc.), instrument readings (values ​​of specific activity and each radionuclide or specific effective activity of NRN in material) with an error estimate, the result of determining the value of A eff.p, a preliminary conclusion about the class of the material. must be assigned to the following class. 4.2 Laboratory method 4.2.1 Purpose of the method The laboratory method is intended for: i); - clarification of the class of building material (product) in case of obtaining boundary values ​​using the express method; - certification of products. 4.2.2 Means of control 4.2.2.1 and characteristics: - the energy range of the detected gamma radiation from 0.1 to 3 MeV; - the lower limit for determining the specific activity of each NRN is not more than 50 Bq / kg; not more than 20% with a confidence level of 0.95.4.2.2.2 A set of certified measures (standard samples) of specific activity NRN.4.2.2.3 Auxiliary equipment: - a set of containers for weighed portions of material of a specified volume with lids and; - laboratory shot a fork; - a control with an ito with round holes and holes with a diameter of 5 mm; - scales for desktop dials in accordance with GOST 29329 or laboratory e in accordance with GOST 24104. 4.2.2.3. (Revised edition, Rev. No. 1). 4.2.2.4 The radiometric installation must have a certificate of state metrological attestation and a duly certified procedure for performing measurements of specific activity and NRN.4.2.3. The order of preparation and equipment for monitoring The preparation of the radiometric installation for measurements and measurements are carried out in accordance with the procedure for performing measurements.4.2.4. Control procedure 4.2.4.1 Sampling and preparation of samples Determination of specific activities of NRN in bulk materials is carried out on test portions taken from a representative sample. A representative sample is obtained by mixing and quartering at least 10 point samples taken from the control points specified in 4.1.4.1 and 4.1.4.2. Sampling is carried out in accordance with the requirements of the current regulatory documents. A representative sample with a grain size of more than 5 mm is ground to a grain size of less than 5 mm. Depending on the volume of the container used in the radiometric installation, a sample weighing from 2.5 to 10 kg is packed in a double bag, between the walls of which a sample passport is placed with the name of the material, the address of the enterprise that sent the sample, places and dates of sampling. Determination of specific activities of NRN in building products and facing materials made of natural stone are also carried out on samples taken from a representative sample. A representative sample weighing from 2.5 to 10 kg is obtained by grinding products (bricks, slabs, near natural stone, obtained by in the production of facing materials) selected upon acceptance of the batch in accordance with the current regulatory documents. It is allowed to use the material obtained when determining the strength limit and in compression, tension and or bending of products, or specially prepared samples. A representative sample with a grain size of less than 5 mm is packed in a double bag, as indicated above. To determine the NPH specific activities, the obtained representative samples are dried to constant weight, then five containers are filled and the containers are weighed. Bulk density is determined by dividing the sample weight in each container by the volume of the container. Containers are hermetically sealed, labeled and kept in room conditions within the time specified by the procedure for performing measurements to obtain radioactive equilibrium NPH.4.2.4.2 Containers with weighed portions are sequentially installed in the radiometric installation and measurements are carried out in accordance with the procedure for performing measurements. 4.2.5 Rules for processing and reporting measurement results measurements and control NRN activities in a representative sample are taken as the arithmetic mean values ​​of the specific activities of each radionuclide (A j) for five and weighed portions:

where i = 1, 2, ..., n ¾ sample number. The absolute error in determining the value of A j is calculated by the formula

(4)

Where a j is the absolute error in determining the specific activity of the jth radionuclide in sample portions, estimated in accordance with the method of performing measurements on a radiometric installation. 4.2.5.3 The value of the specific effective activity NRN (A eff) for a representative sample is calculated in accordance with formula (1) using the values ​​of A j for each radionuclide. The absolute error in determining the values ​​of A eff is calculated by the formula

4.2.5.4 The result of determining the specific effective activity of NRN in the controlled material and establishing the class of the material is taken as the value determined by the formula

(6)

4.2.5.5 The results of determining the specific effective activity of the NRN in the materials are recorded in a log, which should indicate: - the name of the material; - the name of the manufacturer or consumer; - location sampling points; - dates of sampling and measurements; - specific activities of radium, potassium, thorium with errors; - specific effective activity with errors; - name, position and signature of the person who carried out the measurements. 4.2.5.6 The results of testing the material are documented in the form of a test report in the form given in Appendix B.

APPENDIX A

(mandatory)

Criteria for deciding on the use of building materials in accordance with hygienic standards

Specific effective activity (A eff), Bq/kg

Material class

Application area

Up to 370 All types of construction
St. 370 to 740 Road construction within populated areas and zones of promising development, construction of production facilities
From 740 to 1500 road construction outside settlements
St. 1500 to 4000 The issue of using the material is decided in agreement with the State Committee for Sanitary and Epidemiological Supervision
Note - If necessary, in the national standards in force on the territory of the state, the value of the specific effective activity of natural radionuclides can be changed within the limits indicated in the table. (Changed edition, Rev. No. 1, 2).

JOURNAL OF RADIATION MONITORING
BUILDING MATERIALS (PRODUCTS)

Number
control point j

Binding
checkpoint

Conditions
measurements, t ° С, air humidity

Point measurement results

measurement number i

readings rad iometer a A eff. i

error D

The result of determining the specific effective activity of NRN in building materials (products) A eff.p _______________________ Conclusion on the class of material ______________________________

APPENDIX B

TEST REPORT
ON THE DETERMINATION OF THE SPECIFIC EFFECTIVE ACTIVITY OF NRN IN BUILDING MATERIALS (PRODUCTS)

1 Name of the organization and department that carried out the measurements, number of the accreditation certificate (certificate of state metrological attestation of the radiometric installation) 2 Date of the measurement 3 Method of measurement 4 Name of the material (GOST, TU) 5 Name of the manufacturer or consumer enterprise6 Number and location of control points7 Measurement results of a representative sample (number of the test report according to the work log)

Number
hitch and

Specific activity, Bq/kg

Error
definition

Note - Data on activities are given with an indication of errors.
and measurements.8 Conclusion on the material class ____________________________9 Position and signature of the person responsible for the measurements
_____________________________________________________________________________

APPENDIX D

DETERMINATION OF SPECIFIC EFFECTIVE ACTIVITY
ROCKS IN THE QUARRY

Control points and along the bottom of the pit are located at the nodes of a rectangular network 10 ´ 10 m. Control points on the roof and the bottom of the ledge are located along the profile with an interval of no more than 10 m. or from the edge of the ledge - from 1 to 5 m. To take into account the influence of lateral radiation from ledges with a height of more than 1 m, the measured value of A eff should be divided by the correction factor given below. Control points and on the slope of the ledge are located along the profile along the front of work with an interval of no more than 10 m at a profile height from the bottom of the ledge of at least 1 m. The correction factor at a height of 1 m is 1.45. 370 Bq/kg, the sampling interval should be reduced to delineate anomalous areas in order to classify rocks as II, III or IV classes of building materials in accordance with the requirements and given in Appendix A. Key words: inorganic bulk building materials spruce materials, waste industrial production, specific effective activity of natural rad ions

INTERSTATE STANDARD

DETERMINATION OF THE SPECIFIC EFFECTIVE ACTIVITY OF NATURAL RADIONUCLIDES

Official edition

INTERSTATE SCIENTIFIC AND TECHNICAL COMMISSION FOR STANDARDIZATION, TECHNICAL REGULATION AND CERTIFICATION IN CONSTRUCTION (ISTC) Moscow

Foreword

1 DEVELOPED by the NIISF Institute with the participation of VNIPIIstroysyrye of the Russian Federation INTRODUCED by the Gosstroy of Russia

2 ADOPTED by the Interstate Scientific and Technical Commission for Standardization and Technical Regulation in Construction (MNTKS) on March 14, 1994

Amendment No. 1 was adopted by the Interstate Scientific and Technical Commission for Standardization, Technical Regulation and Certification in Construction (MNTKS) on 10.12.97

Amendment No. 2 was adopted by the Interstate Scientific and Technical Commission for Standardization, Technical Regulation and Certification in Construction (MNTKS) on May 17, 2000

Registered by the IGU Standards Bureau No. 3691

State name

Body name government controlled construction

The Republic of Azerbaijan

Gosstroy of the Republic of Azerbaijan

Republic of Belarus

Ministry of Construction and Architecture of the Republic of Belarus

The Republic of Kazakhstan

Construction Committee of the Ministry of Energy, Industry and Trade of the Republic of Kazakhstan

Republic of Kyrgyzstan

State Committee under the Government of the Kyrgyz Republic for Architecture and Construction

The Republic of Moldova

Ministry environment and improvement of the territories of the Republic of Moldova

the Russian Federation

Gosstroy of Russia

The Republic of Tajikistan

Committee for Architecture and Construction of the Republic of Tajikistan

The Republic of Uzbekistan

Goskomarchitektstroy of the Republic of Uzbekistan

3 INTRODUCED FOR THE FIRST TIME

4 ENTERED INTO EFFECT on January 1, 1995 as the state standard of the Russian Federation by Decree of the Gosstroy of Russia dated June 30, 1994 No. 18-48

5 EDITION (March 2007) with Amendments No. 1, 2, adopted in February 1998, December 2000 (IUS 5-98, 5-2001)

© Standards Publishing House, 1995 © Standartinform, 2007

This International Standard may not, in whole or in part, be reproduced, duplicated or distributed as official publication without permission federal agency for technical regulation and metrology

GOST 30108-94

INTERSTATE STANDARD

BUILDING MATERIALS AND PRODUCTS

Determination of specific effective activity of natural radionuclides

Building materials and elements.

Determination of specific activity of natural radioactive nuclei

Introduction date 1995-01-01

1 area of ​​use

This standard applies to inorganic bulk building materials (crushed stone, gravel, sand, cement, gypsum, etc.) and building products (facing, decorative and other products made of natural stone, bricks and wall stones), as well as industrial waste, used directly as building materials or as raw materials for their production, and establishes methods for determining the specific effective activity of natural radionuclides for assessing building materials and products in accordance with the requirements given in Appendix A, and the procedure for monitoring.

GOST 8.326-89* State system measurements. Metrological certification of measuring instruments

GOST 8.513-84** State measurement system. Verification of measuring instruments. Organization and procedure

GOST 24104-88*** Laboratory balance general purpose and exemplary. General specifications

GOST 29329-92 Scales for static weighing. General technical requirements

3 Definitions, symbols and abbreviations

In this standard, the following terms and symbols apply:

Natural radionuclides (NRN) are the main radioactive nuclides of natural origin contained in building materials: radium (226 Ra), thorium (232 Th), potassium (40 K).

The specific activity of a radionuclide (A) is the ratio of the activity of a radionuclide in a sample to the mass of the sample, Bq/kg.

* PR 50.2.009-94 is in force on the territory of the Russian Federation. ** PR 50.2.006-94 is in force on the territory of the Russian Federation. *** On July 1, 2002 GOST 24104-2001 was put into effect.

Official edition

Specific effective activity of NRN (L,ff) - the total specific activity of NRN in the material, determined taking into account their biological effects on the human body according to the formula

A>ff = ^Ra + I '3 1/Iji, + 0.085/4 k, (1)

where /l Ra , A T1]1 A k are the specific activities of radium, thorium, and potassium, respectively, Bq/kg.

4 Methods for determining the specific effective activity of natural radionuclides

This International Standard establishes express and laboratory methods for determining the specific effective activity of NRN in building materials and products.

4.1 Express method

4.1.1 Purpose of the method

Express method is intended for carrying out:

Periodic and input control of bulk building materials and industrial waste (hereinafter referred to as bulk materials), as well as building products in accordance with current regulatory documents;

Preliminary assessment of developed rocks in a quarry (Appendix D).

The condition for the use of the express method is the absence of contamination of materials and

products with technogenic radionuclides.

4.1.2 Controls

4.1.2.1 Portable NRN specific effective activity radiometers using the gamma spectrometric measurement method (for example, RKP-305MS type), with the following technical characteristics:

The lower limit for determining the value of A eff is not more than 100 Bq/kg;

The relative error in determining the value of A eff is not more than 30%.

4.1.2.2 Reference radionuclide source with activity from 100 to 1000 Bq to check the reproducibility of radiometer readings.

4.1.2.3 The radiometric equipment used must be subject to mandatory state metrological tests in accordance with GOST 8.326 and GOST 8.513, confirmed by a certificate of state metrological attestation, and be completed with measurement procedures certified in the prescribed manner, ensuring the introduction of the necessary corrections and an assessment of the error in the results under real measurement conditions.

(Revised edition, Rev. No. 1).

4.1.3 The procedure for preparing the equipment for measurements and monitoring its performance

Preparation of equipment for measurements is carried out in accordance with the instructions for its operation.

To check the operation of the equipment, before and after the performance of working measurements, measurements are taken using a control source. The difference in readings between these measurements should not exceed 5%.

4.1.4 Control procedure

4.1.4.1 When controlling bulk materials in a warehouse, control points are selected:

On cones or stacks - along the perimeters of horizontal sections with an interval of no more than 10 m, the height of the lower section from the base of the cone or stack must be at least 1 m;

On the alluvium map - at the nodes of a rectangular network 10 x 10 m.

4.1.4.2 When incoming control of bulk building materials, control points are selected in each vehicle at a distance of at least 1 m from the side wall:

In railway transport (gondola car and platform) - at least two points;

AT road transport- one point in the center of the body;

On water transport (on a barge - platform or bunker ships) - at least two points located along the axis of the vessel.

4.1.4.3 When inspecting construction products, they form a rectangular prism with a base of at least 1.2 x 1.2 m and a height of 0.5 m, or choose a pallet (package) of products not laid in a herringbone pattern, with dimensions not less than specified, and a control point is selected in the center of the upper plane of the products.

4.1.4.4 Measurements are carried out by installing the radiometer detection unit in the control room.

point on a flat surface of the material. The surface is taken as a flat one, on which the dimensions of the protrusions (cavities) do not exceed the diameter of the detection unit.

At each control point, at least three consecutive measurements are carried out.

4.1.4.5 To reduce the effect of side radiation on the results of measurements, measurements should be carried out at a distance of at least 20 m from buildings, structures, rock masses and building materials and products.

4.1.5 Rules for processing measurement results

4.1.5.1 The result of determining the value of A e ff at the control point is taken as the value determined by the formula

„ X ^eff.g + A

(2)

where / \u003d 1.2 ..... n is the number of measurement at a given point;

n is the number of measurements at a given point (u > 3);

D, ff l - the value of A, ff at the /-th measurement;

D - absolute measurement error, estimated in accordance with the measurement procedure.

4.1.5.2 The result of determining the specific effective activity of NRN in a batch of material (P eff p) is taken as the maximum of the values ​​of D, ff. t.c. obtained from measurements at the control points of a given batch.

4.1.6 Rules for registration of control results

The instrument readings and control results are recorded in the log in the form of Appendix B.

The log records the date of the control, the name of the material (product), the binding of the measurement control points, the characteristics of the measurement conditions (distance from the source of side radiation, air temperature, etc.), instrument readings (values ​​of the specific activity of each radionuclide or the specific effective activity of NRN in the material ) with an estimate of the error, the result of determining the value of I eff n, a preliminary conclusion about the class of material.

If the value A determined during the control is equal to the upper limit value set for the corresponding class, the material must be assigned to the next class.

4.2 Laboratory method

4.2.1 Purpose of the method

The laboratory method is intended for:

Establishing the class of building material (product);

Refinements of the class of building material (product) in case of obtaining boundary values ​​using the express method;

Product certifications.

4.2.2 Controls

4.2.2.1 Radiometric setup based on a stationary gamma spectrometer with the following technical characteristics:

The energy range of the registered gamma radiation is from 0.1 to 3 MeV;

The lower limit for determining the specific activity of each NRN is not more than 50 Bq/kg;

The relative error in determining the specific activity of NRN is not more than 20% at a confidence level of 0.95.

4.2.2.2 Set of certified measures (standard samples) of NRN specific activity.

4.2.2.3 Auxiliary equipment:

A set of containers for weighing material of a specified volume with lids;

Laboratory crusher;

Control sieve with round holes diameter 5 mm;

Drying cabinet;

Desktop dial scales according to GOST 29329 or laboratory scales according to GOST 24104.

4.2.2.4 The radiometric installation must have a certificate of state metrological certification and a duly certified procedure for performing measurements of NRN specific activity.

4.2.3 The procedure for preparing equipment for testing

Preparation of the radiometric setup for measurements and measurements are carried out in accordance with the measurement procedure.

4.2.4 Control procedure

4.2.4.1 Sampling and preparation

The determination of the specific activities of NRN in bulk materials is carried out on test portions taken from a representative sample.

A representative sample is obtained by mixing and quartering at least 10 incremental samples taken from the control points specified in 4.1.4.1 and 4.1.4.2. Sampling is carried out in accordance with the requirements of current regulatory documents. A representative sample with a grain size of more than 5 mm is crushed to a grain size of less than 5 mm. Depending on the volume of the container used in the radiometric installation, a sample weighing from 2.5 to 10 kg is packed in a double bag, between the walls of which a sample passport is placed with the name of the material, the address of the enterprise that sent the sample, the place and date of sampling.

Determination of the specific activities of NRN in building products and facing materials made of natural stone is also carried out on samples taken from a representative sample.

A representative sample weighing from 2.5 to 10 kg is obtained by grinding products (bricks, slabs, natural stone frames obtained during the production facing materials) selected upon acceptance of the batch in accordance with the applicable regulatory documents. It is allowed to use the material obtained by determining the compressive, tensile or bending strength of products, or specially prepared samples.

A representative sample with a grain size of less than 5 mm is packed in a double bag as above.

To determine the specific activities of NPH, the obtained representative samples are dried to constant weight, then five containers are filled and the containers are weighed. Bulk density is determined by dividing the sample weight in each container by the volume of the container.

The containers are hermetically sealed, labeled and kept at room conditions for the time specified in the procedure for performing measurements to obtain the NRN radioactive equilibrium.

4.2.4.2 Containers with weights are successively installed in the radiometric setup and measurements are taken in accordance with the measurement procedure.

4.2.5 Rules for the processing and presentation of measurement and control results

4.2.5.1 The results are processed and the measurement error is assessed in accordance with the measurement procedure separately for each sample and for each of the NRN.

4.2.5.2 As the results of measurements of the specific activities of NRN in a representative sample, the arithmetic mean values ​​of the specific activities of each radionuclide (Hy) for five samples are taken

(3)

where i = 1, 2, . . . , n - sample number.

The absolute error in determining the value of Aj is calculated by the formula

(4)

where a.j is the absolute error in determining the specific activity of the i-th radionuclide in sample portions, estimated in accordance with the procedure for performing measurements on a radiometric installation.

4.2.5.3 The value of the specific effective activity NPH (Aff) for a representative sample is calculated in accordance with formula (1) using the values ​​of Aj for each radionuclide. The absolute error in determining the values ​​of A, ff is calculated by the formula

L \u003d ^ A ^ a + 1.7- A ^ h + 0.007.

4.2.5.4 The result of determining the specific effective activity of NRN in the controlled material and establishing the class of the material is taken as the value determined by the formula

Dff.m = L>ff + A (6)

4.2.5.5 The results of determining the specific effective activity of NRN in materials are recorded in a log, which should indicate:

Name of material;

Name of the manufacturer or consumer enterprise;

Location of sampling points;

Dates of sampling and measurements;

Specific activities of radium, potassium, thorium with errors;

Specific effective activity with error;

Surname, position and signature of the person who carried out the measurements.

4.2.5.6 The results of testing the material are drawn up in the form of a test report in the form given in Appendix B.

APPENDIX A

(mandatory)

Criteria for deciding on the use of building materials in accordance with hygienic standards

(Temporary criteria for the organization of control and decision-making, approved by the Chief State Sanitary Doctor of the USSR A.I. Kondrusev, No. 5789-91 of 10.06.91)

Note - If necessary, in the national standards in force on the territory of the state, the value of the specific effective activity of natural radionuclides can be changed within the limits specified in the table.

Appendix A. (Changed edition, Rev. No. 1, 2).

Journal of radiation monitoring of building materials (products)

Measured material, batch, vehicle_

Operator

The result of determining the specific effective activity of NRN in building materials (products) Deff.p_

Material Grade Conclusion

Test report to determine the specific effective activity of NRN in building materials (products)

1 Name of the organization and department that carried out the measurements, number of the accreditation certificate (certificate of state metrological certification of the radiometric installation)_

2 Date of measurement_

3 Measurement Method_

4 Material name (GOST, TU)_

5 Name of manufacturer or consumer

6 Number and location of control points_

7 Measurement results of a representative sample (number of the test report according to the work log)

Note - Data on activities are given with indication of measurement errors.

8 Conclusion about material class_

9 Position and signature of the person responsible for carrying out the measurements_

Determination of the specific effective activity of rocks in a quarry

Control points along the bottom of the quarry are located at the nodes of a rectangular network 10 x 10 m.

Control points on the roof and the bottom of the ledge are located along the profile with an interval of no more than 10 m. The distance between the profiles should be from 5 to 10 m, the distance of the profile from the edge of the ledge - from 1 to 5 m.

To take into account the influence of lateral radiation from ledges with a height of more than 1 m, the measured value of A eff should be divided by the correction factor given below.

Control points on the slope of the ledge are located along the profile along the work front with an interval of no more than 10 m at a profile height of at least 1 m from the bottom of the ledge. The correction factor for a height of 1 m is 1.45.

At values ​​of Deff > 370 Bq/kg, the sampling interval should be reduced to delineate anomalous areas in order to assign rocks to II, III or IV classes of building materials in accordance with the requirements given in Appendix A.

UDC 691.001.4:006.354 MKS 91.100.01 Zh19 OKSTU 5907

Keywords: inorganic bulk building materials, industrial waste, specific effective activity of natural radionuclides

Editor L.V. Koretnikova Technical editor V.N. Prusakova Proofreader M.S. Kabashova Computer layout I.A. Naleykina

Signed for publication on March 28, 2007. Format 60 x 84 1/s. Offset paper. Headset Times. Offset printing. Uel. pech.l. 1.40. Uch.-ed.l. 0.87. Circulation 108 copies. Zach. 303. From 3895.

FSUE "STANDARTINFORM", 123995 Moscow, Granatny per., 4.

Typed in FSUE "STANDARTINFORM" on a PC.

Printed in the branch of FSUE "STANDARTINFORM" - type. "Moscow printer", 105062 Moscow, Lyalin per., 6.

GOST 30108-94

UDC 691.001.4:006.354

Group G19

INTERSTATE STANDARD

BUILDING MATERIALS AND PRODUCTS

Determination of specific effective activity

natural radionuclides

Building materials and elements.

Determination of specific activity of natural radioactive nuclei

MKS 91.100.01

Introduction date 1995-01-01

Foreword

1 DEVELOPED by the NIISF Institute with the participation of VNIPIIstroysyrye of the Russian Federation

INTRODUCED by Gosstroy of Russia

2 ADOPTED by the Interstate Scientific and Technical Commission for Standardization and Technical Regulation in Construction (MNTKS) on March 14, 1994

State name

The Republic of Azerbaijan

Republic of Armenia

State Architecture of the Republic of Armenia

Republic of Belarus

Gosstroy of the Republic of Belarus

The Republic of Kazakhstan

Ministry of Construction of the Republic of Kazakhstan

Kyrgyz Republic

Gosstroy of the Kyrgyz Republic

The Republic of Moldova

Ministry of Architecture of the Republic of Moldova

the Russian Federation

Gosstroy of Russia

The Republic of Tajikistan

The Republic of Uzbekistan

Amendment No. 1 was adopted by the Interstate Scientific and Technical Commission for Standardization, Technical Regulation and Certification in Construction (MNTKS) on 10.12.97

State name

Name of the public administration body for construction

The Republic of Azerbaijan

Gosstroy of the Republic of Azerbaijan

Republic of Armenia

Ministry of Urban Development of the Republic of Armenia

Republic of Belarus

Ministry of Construction and Architecture of the Republic of Belarus

The Republic of Kazakhstan

Agency for Construction and Architectural and Urban Planning Control of the Ministry of Economy and Trade of the Republic of Kazakhstan

Kyrgyz Republic

Minarchstroy of the Kyrgyz Republic

the Russian Federation

Gosstroy of Russia

The Republic of Tajikistan

Gosstroy of the Republic of Tajikistan

Amendment No. 2 was adopted by the Interstate Scientific and Technical Commission for Standardization, Technical Regulation and Certification in Construction (MNTKS) on May 17, 2000

Registered by the IGU Standards Bureau No. 3691

State name

Name of the public administration body for construction

The Republic of Azerbaijan

Gosstroy of the Republic of Azerbaijan

Republic of Belarus

Ministry of Construction and Architecture of the Republic of Belarus

The Republic of Kazakhstan

Construction Committee of the Ministry of Energy, Industry and Trade of the Republic of Kazakhstan

Republic of Kyrgyzstan

State Committee under the Government of the Kyrgyz Republic for Architecture and Construction

The Republic of Moldova

Ministry of Environment and Territory Improvement of the Republic of Moldova

the Russian Federation

Gosstroy of Russia

The Republic of Tajikistan

Committee for Architecture and Construction of the Republic of Tajikistan

The Republic of Uzbekistan

Goskomarchitektstroy of the Republic of Uzbekistan

3 INTRODUCED FOR THE FIRST TIME

4 ENTERED INTO EFFECT on January 1, 1995 as the state standard of the Russian Federation by the Decree of the Gosstroy of Russia dated June 30, 1994. No. 18-48

5 EDITION (April 2003) with Amendments No. 1, 2, adopted in February 1998, December 2000 (IUS 5-98, 5-2001)

1 area of ​​use

This standard applies to inorganic bulk building materials (crushed stone, gravel, sand, cement, gypsum, etc.) and building products (facing, decorative and other products made of natural stone, bricks and wall stones), as well as industrial waste, used directly as building materials or as raw materials for their production, and establishes methods for determining the specific effective activity of natural radionuclides for assessing building materials and products in accordance with the requirements given in Appendix A, and the procedure for monitoring.

GOST 8.326-89* State measurement system. Metrological certification of measuring instruments

GOST 8.513-84** State measurement system. Verification of measuring instruments. Organization and procedure

GOST 24104-88*** Laboratory scales for general purposes and exemplary. General specifications

GOST 29329-92 Scales for static weighing. General technical requirements

_________________

* PR 50.2.009-94 is in force on the territory of the Russian Federation.

** PR 50.2.006-94 is in force on the territory of the Russian Federation.

In this standard, the following terms and symbols apply:

Natural radionuclides (NRN)- the main radioactive nuclides of natural origin contained in building materials: radium (226 Ra), thorium (232 Th), potassium (40 K);

The specific activity of the radionuclide (BUT) - the ratio of the activity of the radionuclide in the sample to the mass of the sample, Bq/kg;

Specific effective activity NRN ()- the total specific activity of NRN in the material, determined taking into account their biological effect on the human body according to the formula

where , , are the specific activities of radium, thorium, potassium, respectively, Bq/kg.

This International Standard establishes express and laboratory methods for determining the specific effective activity of NRN in building materials and products.

4.1 express method

4.1.1 Purpose of the method

Express method is intended for carrying out:

Periodic and input control of bulk building materials and industrial waste (hereinafter referred to as bulk materials), as well as building products in accordance with current regulatory documents;

Preliminary assessment of developed rocks in a quarry (Appendix D).

The condition for using the express method is the absence of contamination of materials and products with technogenic radionuclides.

4.1.2 Controls

4.1.2.1 Portable NRN specific effective activity radiometers using the gamma spectrometric measurement method (for example, RKP-305MS type), with the following technical characteristics:

The lower limit for determining the value is not more than 100 Bq/kg;

The relative error in determining the value is not more than 30%.

4.1.2.2 Reference radionuclide source with activity from 100 to 1000 Bq to check the reproducibility of radiometer readings.

4.1.2.3 The radiometric equipment used must be subject to mandatory state metrological tests in accordance with GOST 8.326 and GOST 8.513, confirmed by a certificate of state metrological certification, and be completed with measurement procedures certified in the prescribed manner, ensuring the introduction of the necessary corrections and an assessment of the error in the results in real measurements .

(Changed edition, Rev. No. 1)

4.1.3 The procedure for preparing the equipment for measurements and monitoring its performance

Preparation of equipment for measurements is carried out in accordance with the instructions for its operation.

To check the operation of the equipment, before and after the performance of working measurements, measurements are taken using a control source. The difference in readings between these measurements should not exceed 5%.

4.1.4 Control procedure

4.1.4.1 When controlling bulk materials in a warehouse, control points are selected:

On cones or stacks - along the perimeters of horizontal sections with an interval of no more than 10 m, the height of the lower section from the base of the cone or stack must be at least 1 m;

On the alluvium map - at the nodes of a rectangular network 10×10 m.

4.1.4.2 When incoming control of bulk building materials, control points are selected in each vehicle at a distance of at least 1 m from the side wall:

In railway transport (gondola car and platform) - at least two points;

In road transport - one point in the center of the body;

On water transport (on a barge - platform or bunker ships) - at least two points located along the axis of the vessel.

4.1.4.3 When inspecting building products, they form a rectangular prism with a base of at least 1.2×1.2 m and a height of 0.5 m, or choose a pallet (package) of products not laid in a herringbone pattern, with dimensions of at least specified and in the center of the upper plane of the products, a control point is selected.

4.1.4.4 Measurements are carried out by installing the radiometer detection unit at a control point on a flat surface of the material. The surface is taken as a flat one, on which the dimensions of the protrusions (cavities) do not exceed the diameter of the detection unit.

At each control point, at least three consecutive measurements are carried out.

4.1.4.5 To reduce the effect of side radiation on the results of measurements, measurements should be carried out at a distance of at least 20 m from buildings, structures, rock masses and building materials and products.

4.1.5 Rules for processing measurement results

4.1.5.1 The value determined by the formula is taken as the result of determining the value at the control point:

, (2)

4.1.5.2 The result of determining the specific effective activity of NRN in a batch of material () is taken as the maximum of the values ​​obtained during measurements at the control points of this batch.

4.1.6 Rules for registration of control results

The instrument readings and control results are recorded in the log in the form of Appendix B.

The log records the date of the control, the name of the material (product), the binding of the measurement control points, the characteristics of the measurement conditions (distance from the source of side radiation, air temperature, etc.), instrument readings (values ​​of the specific activity of each radionuclide or the specific effective activity of NRN in the material ) with an estimate of the error, the result of determining the value of , a preliminary conclusion about the class of the material.

If the value determined during the control is equal to the upper limit value set for the corresponding class, the material must be assigned to the next class.

4.2 laboratory method

4.2.1 Purpose of the method

The laboratory method is intended for:

Establishing the class of building material (product);

Refinements of the class of building material (product) in case of obtaining boundary values ​​using the express method;

Product certifications.

4.2.2 Controls

4.2.2.1 Radiometric setup based on a stationary gamma spectrometer with the following technical characteristics:

The energy range of the registered gamma radiation is from 0.1 to 3 MeV;

The lower limit for determining the specific activity of each NRN is not more than 50 Bq/kg;

The relative error in determining the specific activity of NRN is not more than 20% at a confidence level of 0.95.

4.2.2.2 Set of certified measures (standard samples) of NRN specific activity.

4.2.2.3 Auxiliary equipment:

A set of containers for weighing material of a specified volume with lids;

Laboratory crusher;

Control sieve with round holes 5 mm in diameter;

Drying cabinet;

Desktop dial scales according to GOST 29329 or laboratory scales according to GOST 24104.

4.2.2.4 The radiometric installation must have a certificate of state metrological certification and a duly certified procedure for performing measurements of NRN specific activity.

4.2.3 The procedure for preparing equipment for testing

Preparation of the radiometric setup for measurements and measurements are carried out in accordance with the measurement procedure.

4.2.4 Control procedure

4.2.4.1 Sampling and preparation

The determination of the specific activities of NRN in bulk materials is carried out on test portions taken from a representative sample.

A representative sample is obtained by mixing and quartering at least 10 incremental samples taken from the control points specified in 4.1.4.1 and 4.1.4.2. Sampling is carried out in accordance with the requirements of current regulatory documents. A representative sample with a grain size of more than 5 mm is crushed to a grain size of less than 5 mm. Depending on the volume used in the radiometric installation of the container, a sample weighing from 2.5 to 10 kg is packed in a double bag, between the walls of which a sample passport is placed with the name of the material, the address of the enterprise that sent the sample, the place and date of sampling.

Determination of the specific activities of NRN in building products and facing materials made of natural stone is also carried out on samples taken from a representative sample.

A representative sample weighing from 2.5 to 10 kg is obtained by grinding products (bricks, slabs, natural stone frames obtained in the production of facing materials) selected upon acceptance of a batch in accordance with current regulatory documents. It is allowed to use the material obtained by determining the compressive, tensile or bending strength of products, or specially prepared samples.

A representative sample with a grain size of less than 5 mm is packed in a double bag as above.

To determine the specific activities of NPH, the obtained representative samples are dried to constant weight, then five containers are filled and the containers are weighed. Bulk density is determined by dividing the sample weight in each container by the volume of the container.

The containers are hermetically sealed, labeled and kept at room conditions for the time specified in the procedure for performing measurements to obtain the NRN radioactive equilibrium.

4.2.4.2 Containers with weights are successively installed in the radiometric setup and measurements are taken in accordance with the measurement procedure.

4.2.5 Rules for the processing and presentation of measurement and control results

4.2.5.1 The results are processed and the measurement error is assessed in accordance with the measurement procedure separately for each sample and for each of the NRN.

4.2.5.2 As the results of measurements of the specific activities of NRN in a representative sample, the arithmetic mean values ​​of the specific activities of each radionuclide () for five samples are taken:

where i = 1, 2, ..., n- mount number.

The absolute error in determining the value is calculated by the formula

, (4)

4.2.5.3 The value of the specific effective activity NPH () for a representative sample is calculated in accordance with formula (1) using the values ​​for each radionuclide.

The absolute error in determining the values ​​is calculated by the formula

4.2.5.4 The result of determining the specific effective activity of NRN in the controlled material and establishing the class of the material is taken as the value determined by the formula

.(6)

4.2.5.5 The results of determining the specific effective activity of NRN in materials are recorded in a log, which should indicate:

Name of material;

Name of the manufacturer or consumer enterprise;

Location of sampling points;

Dates of sampling and measurements;

Specific activities of radium, potassium, thorium with errors;

Specific effective activity with error;

Surname, position and signature of the person who carried out the measurements.

4.2.5.6 The results of testing the material are drawn up in the form of a test report in the form given in Appendix B.

APPENDIX A

(mandatory)

Criteria for deciding on the use of building materials

according to hygiene standards

(Temporary criteria for the organization of control and decision-making, approved by the Chief State Sanitary Doctor of the USSR A.I. Kondrusev, No. 5789-91 of 10.06.91)

Specific effective activity (), Bq / kg

Material class

Application area

All types of construction

St. 370 to 740

Road construction within settlements and zones of promising development, construction of industrial facilities

From 740 to 1500

Road construction outside built-up areas

St. 1500 to 4000

The issue of using the material is decided in agreement with the State Committee for Sanitary and Epidemiological Supervision

Note - If necessary, in the national regulations in force on the territory of the state, the value of the specific effective activity of natural radionuclides can be changed within the limits specified in the table.

(Changed edition, Rev. No. 1, 2)

Journal of radiation monitoring of building materials (products)

Measured material, batch, vehicle ________________________________

______________________________________________________________________________

The date __________________________________________________________________________

Operator ________________________________________________________________________

Device ________________________________________________________________________

The result of determining the specific effective activity of NRN in building materials (products) ________________________________________________________________

Conclusion on the class of material __________________________________________________

Test report to determine the specific effective activity of NRN in building materials (products)

1 Name of the organization and department that carried out the measurements, number of the accreditation certificate (certificate of state metrological certification of the radiometric installation) _________________________________________________________________________

2 Date of measurement ____________________________________________________________

3 Method of measurement ______________________________________________________________

4 Material name (GOST, TU) _____________________________________________

5 Name of the manufacturer or consumer enterprise ________________

6 Number and location of control points ___________________________________

7 Measurement results of a representative sample (number of the test report according to the work log)

Note - Data on activities are given with indication of measurement errors.

8 Conclusion on the class of material __________________________________________________

9 Position and signature of the person responsible for carrying out the measurements __________________

_______________________________________________________________________________

Determination of the specific effective activity of rocks in a quarry

Control points along the bottom of the quarry are located at the nodes of a rectangular network 10 × 10 m.

Control points on the roof and the bottom of the ledge are located along the profile with an interval of no more than 10 m. The distance between the profiles should be from 5 to 10 m, the distance of the profile from the edge of the ledge - from 1 to 5 m.

To take into account the influence of side radiation from ledges with a height of more than 1 m, the measured value should be divided by the correction factor given below.

Control points on the slope of the ledge are located along the profile along the work front with an interval of no more than 10 m at a profile height of at least 1 m from the bottom of the ledge. The correction factor for a height of 1 m is 1.45.

At values ​​>370 Bq/kg, the sampling interval should be reduced to delineate anomalous areas in order to assign rocks to II, III or IV classes of building materials in accordance with the requirements given in Appendix A.

Keywords: inorganic bulk building materials, industrial waste, specific effective activity of natural radionuclides

1 area of ​​use

3 Definitions, symbols and abbreviations

4 Methods for determining the specific effective activity of natural radionuclides

Annex A (mandatory). Criteria for deciding on the use of building materials in accordance with hygienic standards

Specific effective activity A m Eff of natural radionuclides in building materials (sand, crushed stone, cement and brick raw materials, etc.) and industrial waste used for the manufacture of building materials (ash, slag, etc.) is calculated by the formula:

A m Eff \u003d A Ra 226 + 1.31 A T h 232 + 0.085 A K 40 + 0.22 A Cs 137,

Table 6.6.

Specific activity of natural radionuclides in building materials (Bq/kg).

where A Ra - specific activity of radium - 226, A T h - specific activity of thorium - 232 are taken from the table. 6.6, and A to - the specific activity of potassium - 40 and A Cs - the specific activity of cesium - 137 are taken from the table. 6.5 results (converted values).

The obtained values ​​\u200b\u200bof A m Eff are recorded in table. 6.5 results.

The obtained values ​​of the specific effective activity for the studied materials are compared with the values ​​given in Table. 6.4 and draw a conclusion about their applicability.

At A m eff > 1350 Bq kg -1, the use of materials for construction purposes is PROHIBITED.

Conclusions on the work performed

Questions for the test

1. In which houses built from various building materials will the radiation background be the greatest: wooden, brick, concrete?

2. On what factors does the measured value depend radiation background?

3. What radionuclides are usually measured in building material samples?

4. What radionuclide of Chernobyl origin is standardized in samples of building materials?

5. For which construction and natural materials standards introduced?

6. What natural radionuclides are present in building materials?

7. The device and principle of operation of RUG-91?

8. Describe the course of sampling, justify the data and conclusions.

Laboratory work № 7

PROTECTION METHODS FROM IONIZING RADIATION

I. The purpose of the work: Determination of the change in the flux of γ-photons of ionizing radiation depending on the distance. Study of the effectiveness of protection against ionizing radiation various materials(screens).

2. Order of performance of work:

2.1. Study real teaching materials.

2.2. Outline in workbook answers to questions for the report.

2.3. Redraw tables in a notebook and fill them in while working with the device, calculate the data obtained and draw a conclusion about the results of the measurements performed.

EXPOSURE TO IONIZING RADIATION

PER PERSON

A person is constantly exposed to ionizing radiation (IR) due to:

exposure to natural radiation (solar and cosmic radiation, radiation from the bowels of the earth, etc.),

· when working with AI sources at enterprises (institutions), the impact of building walls, etc.

· during medical X-ray and radiological procedures, etc.

But the most massive exposure of people can occur when using nuclear weapons , and also after major accidents at radiation dangerous objects . This requires each person to strictly observe the basics of radiation safety.

In 1896, the Russian physiologist I. R. Tarkhanov showed for the first time that x-rays, passing through living organisms, disrupts their vital activity. Indeed, ionizing radiation turned out to be very dangerous for humans: in 1895, Henri Becquerel received a radiation burn of his hands, in 1902, Marie S. Curie was diagnosed with radiation skin cancer, in 1907, 7 cases of death from ionizing radiation were described. other scientists. The mutagenic effect of ionizing radiation was first established by Russian scientists R.A. Nadson and R.S. Filippov in 1925 in experiments on yeast. In 1927, this discovery was confirmed by R. Meller on a classic genetic object - Drosophila.

Features of the impact of AI on a person are characterized by the following features:

1. Living organisms do not have special organs for recognizing the action of this factor.

2. Ionizing radiation can cause long-term consequences:

malignant tumors,

shortening life,

Decreased immunity.

3. Able to penetrate deeply into the irradiated tissue.

4. Capable of total cumulative action.

5. The damaging effect occurs with negligible amounts of absorbed energy. When a person is irradiated with a lethal dose of γ-radiation equal to 6 Gy, energy is released in his body, approximately equal to: E=mD=70 kg 6 Gy=420 J. Such energy is transferred to the human body with one teaspoon of hot water.

3.1. Irradiation of a person. Currently, penetrating radiation affects the human body as follows:

1. Causes external exposure man by γ-rays from space, from the Earth's surface, from building materials, from Chernobyl radionuclides.

2. The penetration of the gaseous element radon into the atmosphere, and then with inhaled air into the body.

3. The transfer of radioactivity into plants through the roots and their penetration into the human body with food.

Since the energy absorbed by human tissue is small, it is natural to assume that the thermal effect of ionizing radiation is not the direct cause of radiation sickness and human death. Really, The biological effect of ionizing radiation on a living organism is based on chemical processes that occur in living cells after their irradiation. radioactive radiation cause ionization of atoms and molecules living tissue, resulting in breaking normal molecular bonds and change in the chemical structure of cellular macromolecules. These changes lead to either cell death or mutation.

The impact of ionizing radiation on body tissues has several stages:

1. Formation of charged particles. α- and β-particles penetrating into the tissues of the body lose energy due to electrical interactions with the electrons of those atoms near which they pass.
2. Electrical Interactions. Under the influence of penetrating radiation, electrons are detached from the atoms of the body's tissue. They are negatively charged, so the rest of the original neutral atom becomes positively charged. This process is called ionization. The detached electrons can ionize other atoms.
3. Physical and chemical changes. Both a free electron and an ionized atom cannot stay in this state for a long time. Therefore, they enter into a complex chain of reactions, as a result of which new molecules are formed. They include such extremely reactive molecules as "free radicals" (OH - hydroxyl radical, HO 2 - hydroperoxide radical, H 2 O 2 - hydrogen peroxide, O - atomic oxygen, O o - singlet oxygen, etc. ). They have strong oxidizing and toxic properties.
4. chemical changes. The resulting free radicals react both with each other and with other molecules. Entering into connections with organic matter, they cause significant chemical changes in cells and tissues. Chemical composition cell changes as a result of radiolysis of its components or metabolic processes of interaction of various cellular organelles, denaturation of protein and other organic structures with the formation of toxic histamine-like substances. Depolymerization of hyaluronic acid, glyco- and lipoproteins occurs, the permeability of cell membranes, the structure of DNA and RNA are disturbed.
5. biological effects. can occur both in a few seconds and decades after irradiation and cause immediate cell death, or contribute to the development of: 1) early changes in cells that lead to cancer genetic mutations that affect future generations; damage to the fetus and fetus due to exposure of the mother during pregnancy; the development of radiation sickness, characterized by the development of: hemorrhagic syndrome, intestinal syndrome and cerebral syndrome; 2) long-term effects: an increase in the number of cancers, leukemia, an increase in genetic load, a shortening of life expectancy.

The behavior of radionuclides absorbed into the blood is determined by:

one). The importance for the body of stable isotopes of these elements for certain tissues and organs. For example, calcium performs a specific role, is part of the tissues, especially in the skeletal system. Iodine accumulates in the thyroid gland, cesium is an intracellular electrolyte, and so on.

2). Physical and chemical properties of radionuclides - the position of the elements in the periodic system of D.I. Mendeleev, the valence form of the radioisotope and the solubility chemical compound, the ability to form colloidal compounds in the blood and tissues, and other factors.

For all radionuclides, the critical organs are the hematopoietic system and the gonads, because they are the most vulnerable even at low doses of radiation. Radioactive isotopes that have entered the body of animals and humans, as well as stable isotopes of elements, are excreted as a result of metabolism from the body with feces, urine, milk, eggs (chickens, geese) and other ways. Distinguish:

a) direct action- a molecule undergoes changes directly from radiation when a photon or a charged particle passes through it, and the damaging effect is associated with the act of excitation and ionization of atoms and macromolecules (primarily hormones and enzymes). Depending on the dose of absorbed rays, the process of depolymerization of colloidal structures or, conversely, their polymerization can take place.

b) Indirect or indirect action - the molecule receives energy, leading to its changes, from the products of radiolysis of water (H 2 O 2 , O 2 - , OH -) or dissolved substances, and not absorbed by the molecules themselves.

Great importance has energy migration along biopolymer molecules, as a result of which energy absorption that occurs anywhere in a macromolecule leads to damage to its active center (for example, to inactivation of a protein-enzyme). In addition, not all energy transfer by an ionizing particle results in radiation damage. In order to explain this paradox, hit and target principles. According to these principles, there are certain areas (targets) in the cells, hitting which leads to damage. The radiation effect is caused by one or more hits of ionizing particles into the cell. Depending on how many cases of hitting the target are needed to hit the target (one, two, etc.), one-, two-hit, etc. objects are distinguished. The principle of hitting is applied most strictly to the analysis of hitting single-hit objects. In this case, ionizing radiation can cause:

- stochastic (rare) damage, there are no minimum doses for their appearance. As the dose is reduced, the effects are still possible, but their likelihood becomes less. With increasing dose, it is not the severity of these effects that increases, but probability (risk) of their occurrence. The main stochastic consequences are cancers and hereditary genetic defects. The risk factors for their occurrence are presented in Table. 7.1.

The goals and principles of standardization in the Russian Federation are established by the Federal Law of December 27, 2002 No. 184-FZ "On Technical Regulation", and the rules for the application of national standards of the Russian Federation - GOST R 1.0-2004 "Standardization in the Russian Federation. Basic Provisions»

About the standard

1 DEVELOPED by the State Scientific Institution "All-Russian Research, Design and Design and Technological Institute of Organic Fertilizers and Peat" of the Russian Academy of Agricultural Sciences, State Scientific Institution "All-Russian Research Institute of Agrochemistry" named after. D.N. Pryanishnikova Russian Academy Agricultural Sciences, State Scientific Institution "All-Russian Research Institute of Veterinary Sanitation, Hygiene and Ecology" of the Russian Academy of Agricultural Sciences

2 INTRODUCED technical committee according to standardization TC 25 "Quality of soils and soils"

3 APPROVED AND INTRODUCED BY Order No. 1229-st of December 15, 2009 of the Federal Agency for Technical Regulation and Metrology

4 INTRODUCED FOR THE FIRST TIME

Information about changes to this standard is published in the annually published information index "National Standards", and the text of changes and amendments - in the monthly published information indexes "National Standards". In case of revision (replacement) or cancellation of this standard, a corresponding notice will be published in the monthly published information index "National Standards". Relevant information, notification and texts are also placed in the information system common use- on the official website of the Federal Agency for Technical Regulation and Metrology on the Internet

GOST R 53745-2009

NATIONAL STANDARD OF THE RUSSIAN FEDERATION

FERTILIZERS ORGANIC

Methods for determining the specific effective activity of natural radionuclides

organic fertilizers. Methods for determination of specific effective activity of natural radioactive nuclei

Introduction date - 2011-01-01

1 area of ​​use

This standard applies to organic fertilizers, including sapropels, peat from various deposits, and establishes express and laboratory methods for determining the specific effective activity of natural (natural) radionuclides to assess the compliance of organic fertilizers, including sapropels, peat, with radioactive safety standards.

2 Normative references

This standard uses Normative references to the following standards:

4.2 Laboratory method

4.2.1 Purpose of the method

The laboratory method is designed to establish the compliance of organic fertilizers, peat with radiation safety standards.

4.2.2 Measuring instruments

4.2.2.1 Radiometric setup based on a stationary gamma spectrometer (for example, "PROGRESS-GAMMA") with the following technical characteristics:

The energy range of the registered gamma radiation is from 0.1 to 3.0 MeV;

The lower limit of measurements of the specific activity of each NRN is not more than 50 Bq/kg;

The error in measuring the specific activity of NRN is not more than 20% at a confidence level of 0.95.

4.2.2.2 Reference radionuclide source with activity from 100 to 1000 Bq to check the reproducibility of radiometer readings

4.2.2.3 Auxiliary equipment:

A set of containers for weighing organic fertilizers, peat of a fixed volume with lids;

Laboratory crusher;

Control sieve with round holes 5 mm in diameter;

Drying cabinet;

Table dial scales - byGOST 29329or laboratory - according toGOST 24104.

4.2.3 Procedure for preparing equipment for measurements

Preparation of the radiometric setup for measurements and measurements are carried out in accordance with the certified measurement procedure on this radiometric setup.

4.2.4 Measurement procedure

4.2.4.1 Sampling and preparation

Measurement of NRN specific activities in solid types organic fertilizers, peat is carried out on samples taken from a representative sample.

A representative sample is obtained by mixing and quartering at least 10 incremental samples taken from the control points indicated in and . Sampling is carried out in accordance with the requirements of the current regulatory documents. A representative sample with a particle size of more than 5 mm is crushed to a size of less than 5 mm. Depending on the volume used in the radiometric installation of the container, a sample weighing from 2.5 to 10 kg is packed in a double bag, between the walls of which a sample passport is placed with the name of the type of fertilizer, peat, address of the enterprise that sent the sample, place and date of sampling.

Measurement of NRN specific activities in organic fertilizers, peat is also carried out on samples taken from a representative sample.

A representative sample with a particle size of less than 5 mm is packed in a double bag as above.

To measure NPH specific activities, the resulting representative samples are dried to constant weight, then five containers are filled and the containers are weighed. Bulk density is determined by dividing the sample weight in each container by the volume of the container.

4.2.4.2 Containers with weights are sequentially installed in the radiometric setup and measurements are made in accordance with the certified measurement procedure on this radiometric setup.

4.2.5 Processing and presentation of measurement and control results

4.2.5.1 Processing of the results and evaluation of the measurement error is carried out in accordance with the certified measurement procedure on this radiometric unit separately for each sample and for each of the NRN.

4.2.5.2 The arithmetic mean values ​​of the specific activities of each radionuclide ( BUT j) by five weights

where i = 1, 2, ..., n- sample number;

Absolute measurement error BUT j calculated according to the formula

(4)

where Dj - absolute error of measurement of specific activityj-th radionuclide in sample portions, evaluated in accordance with the certified measurement procedure on this radiometric unit.

4.2.5.3 The value of the specific effective activity of NRN (AEFF) for a representative sample is calculated according to the formula () using BUT j, for each radionuclide.

Absolute measurement error A EFF calculated according to the formula

where DRa, DTh and DK - measurement errors, estimated in accordance with the certified measurement procedure for a given measuring instrument.

4.2.5.4 The result of measuring the specific effective activity of NRN in controlled organic fertilizer, peat and establishing their class is taken as the value calculated by the formula

AEFF.M = AEFF + D.(6)

4.2.5.5 The results of measurements of the specific effective activity of NRN in organic fertilizers, peat are recorded in a log, which indicates:

Name of fertilizer, peat;

Name of the manufacturer or consumer enterprise;

Location of sampling points;

Date of sampling and measurements;

Specific activity of radium, potassium, thorium with errors;

Specific effective activity with an error;

Surname, position and signature of the person who carried out the measurements.

4.2.5.6 The results of testing the material are drawn up in the form of a test report in form 2, given in Appendix.

5 Quality control of measurement results

Quality control of measurement results in the laboratory involves checking the stability of measurement results, taking into account the requirementsGOST R ISO 5725-6.

Laboratories that measure the specific effective activity of NRN in organic fertilizers (peat) must comply with the requirementsGOST R ISO/IEC 17025 and .

6 Safety requirements and personnel qualifications

Radiochemists or agricultural chemists working or temporarily involved in radiochemical analysis and the preparation of reference preparations should be guided by -.

When operating radiometers, the rules and requirements must be observed.

Radiochemical analyzes should be performed by personnel with a special higher or secondary chemical education.

Radiometric measurements should be carried out by personnel with the appropriate qualification group for safety when working on electrical installations according to.

All personnel involved in conducting analyzes and radiometric measurements must be approved by medical authorities to work with radioactive sources.

Protocol for measuring the specific effective activity of NRN in organic fertilizer (peat)

A.1 Form 1 of the protocol for measuring the specific effective activity of NRN in organic fertilizer (peat)

Protocol No._______

in organic fertilizer (peat)

Name of organic fertilizer (peat), batch, vehicle

_____________________________________________________________________________

The date_________________________________________________________________________

Operator_____________________________________________________________________

Appliance _____________________________________________________________________________

Checkpoint numberj

Breakpoint Anchor

measurement conditions,t, ° C, air humidity

Measurement No.

Radiometer reading BUT i

Error D

AEFF.T

Measurement errorAEFF.T

The results of measurements of the specific effective activity of NRN in organic fertilizer (peat)AEFF.P

_____________________________________________________________________________

Conclusion on compliance with the requirements of NRB 99/2009_______________________________________________

A.2 Form 2 of the protocol for measuring the specific effective activity of NRN in organic fertilizer (peat)

Protocol No. _______
measurements of the specific effective activity of NRN
in organic fertilizers (peat)

1 Name of the organization and department that carried out the measurements, number of the accreditation certificate

2 Date of measurement

3 Measurement method

4 Name of organic fertilizer (peat)

5 Name of manufacturer or consumer

6 Number and location of control points

7 Measurement results of a representative sample

Sample number

Specific activity, Bq/kg

Measurement error

AEFF.M

226 Ra

232Th

40 K

Sanitary and epidemiological requirements for soil quality

MU 2.6.1.1868-04

Implementation of indicators of radiation safety and conditions of environmental objects, incl. food raw materials and food products, into the system of social and hygienic monitoring

RD 153-34.0-03.150-00

Intersectoral rules on labor protection (safety rules) during the operation of electrical installations. Approved by the Decree of the Ministry of Labor of the Russian Federation of January 5, 2001 No. 3 and the order of the Ministry of Energy of the Russian Federation of December 27, 2000 No. 163

Keywords: organic fertilizers, peat, natural radionuclides, specific activity, specific effective activity, express, laboratory methods, control tools, preparation of instruments, analysis progress, processing of results