INTERSTATE STANDARD

DETERMINATION OF SPECIFIC EFFECTIVE ACTIVITY OF NATURAL RADIONUCLIDES

Official publication

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

Preface

1 DEVELOPED by the NIISF Institute with the participation of VNIPIIstroysyrye Russian Federation INTRODUCED by the State Construction Committee of Russia

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

Change No. 1 was adopted by the Interstate Scientific and Technical Commission for Standardization, Technical Regulation and Certification in Construction (MNTKS) 12/10/97

Change No. 2 was adopted by the Interstate Scientific and Technical Commission for Standardization, Technical Regulation and Certification in Construction (MNTKS) 05/17/2000

Registered by the Bureau of Standards MGS No. 3691

3 INTRODUCED FOR THE FIRST TIME

4 ENTERED INTO EFFECT on January 1, 1995 as state standard Russian Federation by Decree of the State Construction Committee 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 standard may not be reproduced, replicated or distributed in whole or in part. official publication without permission Federal agency By technical regulation and metrology

GOST 30108-94

INTERSTATE STANDARD

CONSTRUCTION MATERIALS AND PRODUCTS

Determination of specific effective activity of natural radionuclides

Building materials and elements.

Determination of specific activity of natural radioactive nuclei

Date of introduction 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 (cladding slabs, decorative and other products from natural stone, bricks and wall stones), as well as for waste industrial production, 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 scales general purpose and exemplary. General technical conditions

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

3 Definitions, symbols and abbreviations

The following terms and symbols are used in this standard:

Natural radionuclides (NRN) are 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) - the ratio of the activity of the radionuclide in the sample to the mass of the sample, Bq/kg.

* PR 50.2.009-94 applies on the territory of the Russian Federation. ** PR 50.2.006-94 applies on the territory of the Russian Federation. *** On July 1, 2002, GOST 24104-2001 came into force.

Official publication

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

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

where /l Ra, А Т1]1 А к - 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

The express method is intended for:

Periodic and incoming inspection of bulk construction materials and industrial waste (hereinafter referred to as bulk materials), as well as construction products in accordance with current regulatory documents;

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

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

products with man-made radionuclides.

4.1.2 Controls

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

The lower limit for determining the value of A eff is no more than 100 Bq/kg;

The relative error in determining the value of A eff is no more than 30%.

4.1.2.2 Control 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 equipped with measurement techniques certified in the established manner, ensuring the introduction of the necessary corrections and assessment of the error of the results under real measurement conditions.

(Changed edition, Amendment No. 1).

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

The equipment is prepared for measurements in accordance with its operating instructions.

To check the operation of the equipment, before and after performing operational 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 monitoring 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 bottom 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 entrance 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 platform barge or bunker vessels) - at least two points located along the axis of the vessel.

4.1.4.3 When carrying out inspection of construction products, a rectangular prism with a base of at least 1.2 x 1.2 m and a height of 0.5 m is formed from them, or a pallet (package) of products not laid in a herringbone pattern is selected, 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 a radiometer detection unit in the control room

point on flat surface material. A surface on which the dimensions of the protrusions (depressions) do not exceed the diameter of the detection unit is taken as flat.

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

4.1.4.5 To reduce the influence of lateral radiation on the results, 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 eff at the control point is taken to be the value determined by the formula

„ X ^eff.g + A

(2)

where / = 1.2....n - measurement number at a given point;

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

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

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

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

4.1.6 Rules for recording inspection results

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

The log records the date of the control, the name of the material (product), the binding of control measurement points, the characteristics of the measurement conditions (distance from the source of lateral 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 error estimate, the result of determining the value of I eff p, a preliminary conclusion about the class of the material.

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

4.2 Laboratory method

4.2.1 Purpose of the method

Laboratory method created for:

Establishing the class of building material (product);

Clarification of the class of building material (product) in case of receipt limit values using the express method;

Product certification.

4.2.2 Controls

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

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

The lower limit for determining the specific activity of each NRN is no more than 50 Bq/kg;

The relative error in determining the specific activity of NRN is no more than 20% with a confidence level of 0.95.

4.2.2.2 A set of certified measures (standard samples) for the specific activity of NRN.

4.2.2.3 Auxiliary equipment:

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

Laboratory crusher;

Test sieve with round holes 5 mm in diameter;

Drying cabinet;

Tabletop dial scales in accordance with GOST 29329 or laboratory scales in accordance with GOST 24104.

4.2.2.4 The radiometric installation must have a certificate of state metrological certification and a procedure for measuring the specific activity of NRN, certified in the prescribed manner.

4.2.3 Procedure for preparing equipment for testing

The preparation of the radiometric installation 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

Determination of specific activities of NRN in bulk materials is carried out on samples taken from a representative sample.

A representative sample is obtained by mixing and quartering at least 10 spot 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 greater than 5 mm is crushed to a grain size 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 packaged 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 rounds obtained during production facing materials), selected upon acceptance of the batch in accordance with the current regulatory documents. It is allowed to use 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 double bagged as above.

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

The containers are hermetically sealed, labeled and kept in room conditions within the time established by the measurement procedure to obtain the radioactive equilibrium of the NRN.

4.2.4.2 Containers with samples are sequentially installed in the radiometric installation and measurements are carried out in accordance with the measurement procedure.

4.2.5 Rules for processing and recording measurement and control results

4.2.5.1 Processing of the results and assessment of the measurement error is carried out in accordance with the measurement procedure separately for each sample and for each of the NRNs.

4.2.5.2 The arithmetic average values ​​of the specific activities of each radionuclide (Hu) for five samples are taken as the results of measurements of the specific activities of NRN in a representative sample

(3)

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

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

(4)

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

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

A = ^ 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 to be 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 journal, which must 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;

Last name, 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

(required)

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

(Temporary criteria for organizing control and decision-making, approved by the Chief State Sanitary Doctor of the USSR A.I. Kondrusev, No. 5789-91 dated 06/10/91)

Note - If necessary, in 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, Amendment 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_

Conclusion about the class of material

Test protocol for determining 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 Name of material (GOST, TU)_

5 Name of the manufacturer or consumer enterprise

6 Number and location of control points_

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

Note - Activity data is provided with measurement errors.

8 Conclusion about the class of material_

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

Determination of 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 of 10 x 10 m.

Control points on the roof and 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 should be from 1 to 5 m.

To take into account the influence of lateral radiation from benches 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 from the bottom of the ledge of at least 1 m. The correction factor for a height of 1 m is 1.45.

For values ​​of Deff > 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 given in Appendix A.

UDC 691.001.4:006.354 MKS 91.100.01 Zh19 OKSTU 5907

Key words: inorganic bulk construction materials, industrial waste, specific effective activity of natural radionuclides

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

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

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

Typed into FSUE "STANDARTINFORM" on a PC.

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

The goals and principles of standardization in the Russian Federation have been established Federal law dated 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"

Standard information

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, the 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 on standardization TC 25 “Quality of soils and soils”

3 APPROVED AND ENTERED INTO EFFECT by Order of the Federal Agency for Technical Regulation and Metrology dated December 15, 2009 No. 1229-st

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 is in the monthly published information indexes "National Standards". In case of revision (replacement) or cancellation of this standard, the corresponding notice will be published in the monthly published information index “National Standards”. Relevant information, notices and texts are also posted 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

ORGANIC FERTILIZERS

Methods for determining the specific effective activity of natural radionuclides

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

Date of introduction - 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 intended to establish the compliance of organic fertilizers and peat with radiation safety standards.

4.2.2 Measuring instruments

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

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

The lower limit for measuring the specific activity of each NRN is no more than 50 Bq/kg;

The error in measuring the specific activity of NRN is no more than 20% with a confidence level of 0.95.

4.2.2.2 Control 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 weighed amounts of organic fertilizers and peat of a specified volume with lids;

Laboratory crusher;

Test sieve with round holes 5 mm in diameter;

Drying cabinet;

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

4.2.3 Procedure for preparing equipment for measurements

The radiometric installation is prepared for measurements and measurements are carried out in accordance with the certified measurement methodology for this radiometric installation.

4.2.4 Measurement procedure

4.2.4.1 Sampling and preparation

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

A representative sample is obtained by mixing and quartering at least 10 spot samples taken from the control points indicated in and. Sampling is carried out in accordance with the requirements of current regulatory documents. A representative sample with a particle size greater than 5 mm is crushed to a size 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 packaged in a double bag, between the walls of which a sample passport is placed with the name of the type of fertilizer, peat, the address of the enterprise that sent the sample, the place and date of sampling.

Measurement of specific activities of NRN 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 double bagged as above.

To measure the specific activities of NRN, 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 mass of the sample in each container by the volume of the container.

4.2.4.2 Containers with samples are sequentially installed in the radiometric installation and measurements are carried out in accordance with the certified measurement procedure for this radiometric installation.

4.2.5 Processing and registration of measurement and control results

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

4.2.5.2 The arithmetic average values ​​of the specific activities of each radionuclide ( ( A j) for five samples

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

Absolute measurement error A j calculated by the formula

(4)

Where Dj - absolute measurement error of specific activityj-th radionuclide in sample samples, assessed in accordance with a certified measurement procedure using a given radiometric installation.

4.2.5.3 The value of the specific effective activity of NRN (AEFF) for a representative sample is calculated in accordance with the formula () using A j, for each radionuclide.

Absolute measurement error of values A EFF calculated by 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 a 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 and peat are recorded in a journal in which they indicate:

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 error;

Last name, 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 agrochemists working or temporarily involved in radiochemical analysis and production of reference preparations should be guided by -.

When operating radiometers, rules and requirements must be observed.

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

Radiometric measurements must be carried out by personnel who have the appropriate qualification group for safety precautions when working on electrical installations according to.

All personnel involved in conducting analyzes and radiometric measurements must be authorized 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

_____________________________________________________________________________

Date of_________________________________________________________________________

Operator_____________________________________________________________________

Device_______________________________________________________________________________

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 specific effective activity of NRN
in organic fertilizers (peat)

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

2 Date of measurement

3 Measurement method

4 Name of organic fertilizer (peat)

5 Name of the manufacturer or consumer enterprise

6 Number and location of control points

7 Measurement results of a representative sample

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

GOST 30108-94

INTERSTATE STANDARD

CONSTRUCTION MATERIALS AND PRODUCTS

DETERMINATION OF SPECIFIC EFFECTIVE
ACTIVITIES OF NATURAL RADIONUCLIDES

GOSSTROY OF RUSSIA

Preface

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

INTERSTATE STANDARD

CONSTRUCTION MATERIALS AND PRODUCTS

Determination of specific effective activity
natural radionuclides

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

Date of introduction 1995-01-01

1 AREA OF USE

2 REGULATORY REFERENCES

3 DEFINITIONS, SYMBOLS AND ABBREVIATIONS

where A Ra, A Th, A k are the specific activities of radium, thorium, potassium, respectively, Bq/kg.

4 METHODS FOR DETERMINING THE SPECIFIC EFFECTIVE ACTIVITY OF NATURAL RADIONUCLIDES

(2)

where i = 1, 2, ..., n - measurement number at a given point; n - number of measurements at a given point (n ³ 3); A eff. i - value of quantity A eff pr and i-th dimension; D is the absolute measurement error, estimated in accordance with the measurement procedure. 4.1.5.2 The result of determining the value of specific effective activity and NER in a batch of material (A eff.p) is taken to be the maximum of the values ​​A eff.t. j obtained during measurements at control points of a given batch. 4.1.6 Rules for recording control results The instrument readings and control results are entered in a log according to the form of Appendix B. The date of control and the name of the material (product) are recorded in the log. , binding of measurement control points, features of measurement conditions (distance from the source of lateral radiation, air temperature, etc.), instrument readings (values ​​of specific activity of each radionuclide or specific effective activity of NRN in material) with an assessment of the error, the result of determining the value of A eff.p, a preliminary conclusion about the class of the material. If the value of A eff.p determined during control is equal to the upper limit value established for the corresponding class, 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: - establishing the class of a building material (product); - clarifying the class of a building material (product) in case of obtaining boundary values ​​using the express method ;- product certification. 4.2.2 Control means 4.2.2.1 Radiometric installation based on a stationary gamma spectrometer with the following technical and characteristics: - energy range of recorded gamma radiation from 0.1 to 3 MeV; - the lower limit for determining the specific activity of each NRN is no more than 50 Bq/kg; - the relative error in determining the specific activity of NRN is no more than 20% with a confidence probability of 0.95.4.2.2.2 A set of certified measures (standard samples) specific activity ERN.4.2.2.3 Auxiliary equipment: - a set of containers for samples of material of a specified volume with lids; - a laboratory crusher; - a control sieve with a round sieve and holes with a diameter of 5 mm; - table-top dial scales according to GOST 29329 or laboratory tests according to GOST 24104. 4.2.2.3. (Changed edition, Amendment No. 1). 4.2.2.4 The radiometer installation must have a certificate of state metrological certification and a duly certified methodology for performing specific activity measurements and ERN.4.2.3. Procedure for preparation and equipment for testing. Preparation of radiometric installations 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 of samples Determination of specific activities of NRN in bulk materials is carried out on weighed portions taken from a representative sample. A representative sample is obtained by mixing and quartering at least 10 spot samples taken from 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 greater 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 packaged 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, place and date of sampling. Determination of specific activities of NRN in building products and facing materials made of natural stone is also carried out on weighed portions selected from a representative sample. A representative sample weighing from 2.5 to 10 kg is obtained by grinding of products (bricks, slabs, near natural stone, obtained 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 by determining the tensile strength and during 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 specific activities of NRN, the obtained representative samples are dried to constant weight, then five containers are filled and the containers are weighed. The bulk density is determined by dividing the mass of the sample in each container by the volume of the container. The containers are hermetically sealed, marked and kept in room conditions for the time established by the measurement procedure to obtain radioactive equilibrium ERN.4.2.4.2 Containers with samples are sequentially installed in a radiometric installation and measurements are carried out in accordance with the measurement procedure. 4.2.5 Rules for processing and recording measurement and control results 4.2.5.1 Processing the results and assessing the error and measurements is carried out in accordance with the measurement procedure separately for each sample and for each of the NRNs. 4.2.5.2 As the results of measurements of the specific activities of NRN in a representative sample, the arithmetic average values ​​of the specific activities of each radionuclide (A j) by weight and weight are taken:

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

(4)

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

(6)

4.2.5.5 The results of determining the specific effective activity of NRN in materials are entered in a journal in which the following must be indicated: - name of the material; - name of the manufacturer or consumer enterprise; - 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

(required)

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

JOURN AL OF RADIATION CONTROL
BUILDING MATERIALS (PRODUCTS)

APPENDIX B

TEST REPORT
BY DETERMINING THE SPECIFIC EFFECTIVE ACTIVITY OF NER 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 the measurement3 Measurement method4 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 (test report number according to the work log)

APPENDIX D

DETERMINATION OF SPECIFIC EFFECTIVE ACTIVITY
ROCKS IN THE QUARRY

Control points along the bottom of the quarry are located at the nodes of a rectangular network of 10 ´ 10 m. Control points on the roof and 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 professional 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 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 from the bottom of the ledge of at least 1 m. The correction factor at a height of 1 m is 1.45. For values ​​A eff > 370 Bq/kg the sampling interval should be reduced to delineate abnormal areas in order to classify rocks as II, III or IV classes of building materials in accordance with the requirements given in Appendix A. Key words: inorganic bulk building materials solid materials, industrial waste, specific effective activity of natural rad ionuclides

Specific effective activity (Aeff) is a parameter characterizing the total specific activity of natural radionuclides in building materials, determined taking into account their biological effects on the human body; measured in becquerels per kilogram (Bq/kg). According to this indicator, materials are divided into classes: Class I - A eff £ 370 Bq/kg, Class II - A eff £ 740 Bq/kg, Class III - A eff

Construction dictionary.

See what “Specific effective activity (Aeff)” is in other dictionaries:

specific effective activity of NRN- Aeff, Bq/kg: Total specific activity of NRN in the material, determined taking into account their biological effect on the human body according to formula (3.2): Aeff = ARa + 1.31 ATh + 0.085 Ak, (2) where ARa, ATh, Ak specific activities of radium, thorium, potassium... ...

specific effective activity NRN A EFF- 3.2 specific effective activity of NER AEFF: Specific effective activity of NER in organic fertilizers, peat, determined taking into account their biological effects on the human body and calculated by the formula AEFF = ARa + 1.31ATh + 0.085Ak,... ... Dictionary-reference book of terms of normative and technical documentation

Aeff- total specific effective activity of natural radionuclides connection Example of use Aeff from 370 to 740 Bq/kg ... Dictionary of abbreviations and abbreviations

GOST R 53745-2009: Organic fertilizers. Methods for determining the specific effective activity of natural radionuclides- Terminology GOST R 53745 2009: Organic fertilizers. Methods for determining the specific effective activity of natural radionuclides original document: 3.1 natural radionuclides NRN: Main radioactive nuclides of natural origin,... ... Dictionary-reference book of terms of normative and technical documentation

GOST R 54748-2011: Crushed stone from dense rocks for the ballast layer of railway tracks. Specifications- Terminology GOST R 54748 2011: Crushed stone from dense rocks for the ballast layer of railway tracks. Specifications original document: analytical sample: A sample of material prepared from laboratory sample and intended for... Dictionary-reference book of terms of normative and technical documentation

GOST 30108-94: Construction materials and products. Determination of specific effective activity of natural radionuclides- Terminology GOST 30108 94: Construction materials and products. Determination of the specific effective activity of natural radionuclides original document: 4.2 Laboratory method 4.2.1 Purpose of the method The laboratory method is intended for: ... ... Dictionary-reference book of terms of normative and technical documentation

Laboratory method- 4.2 Laboratory method 4.2.1 Purpose of the method The laboratory method is intended to: establish the class of a building material (product); clarification of the class of building material (product) in case of obtaining limit values ​​by express... ... Dictionary-reference book of terms of normative and technical documentation

Crushed stone is an inorganic granular bulk material with grains larger than 5 m ... Wikipedia

SANITARY STANDARDS AND RADIATION SAFETY RULES- normative legal acts establishing sanitary requirements on protecting people from radiation exposure. Radiation safety standards (NRB 99) are applied to ensure human safety in all conditions of exposure... ... Russian encyclopedia of labor protection

The 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 = 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 k - specific activity of potassium - 40 and A Cs - specific activity of cesium - 137 are taken from table. 6.5 results (converted values).

Write the obtained values ​​of A m Eff in the table. 6.5 results.

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

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

Conclusions on the work performed

Questions for assessment

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 of background radiation depend?

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

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

5. For what construction and natural materials Have standards been introduced?

6. What natural radionuclides are present in building materials?

7. Design and principle of operation of RUG-91?

8. Describe the process of sample determination, justify the data obtained and conclusions.

Laboratory work No. 7

METHODS OF PROTECTION AGAINST IONIZING RADIATION

I. Purpose of the work: Determination of change in γ-photon flux ionizing radiation depending on distance. Research on the effectiveness of protection against ionizing radiation various materials(screens).

2. Work order:

2.1. Study real teaching materials.

2.2. Take notes in workbook answers to questions for the test.

2.3. Draw tables in a notebook and fill them out 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 sources of AI at enterprises (institutions), exposure to building walls, etc.

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

But the most widespread exposure of people can occur when using nuclear weapons, and also after major accidents at radiation hazardous facilities. This requires each person to strictly adhere to the basics of radiation safety.

In 1896, Russian physiologist I.R. Tarkhanov first showed that X-ray radiation, passing through living organisms, disrupts their vital functions. Indeed, ionizing radiation turned out to be very dangerous for humans: in 1895, Henri Becquerel received radiation burns on his hands, in 1902, radiation skin cancer was detected in Marie S. Curie, in 1907, 7 cases of death from ionizing radiation were described other scientists. The mutagenic effects of ionizing radiation were 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 classical genetic object - Drosophila.

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

1. Living organisms do not have special organs to recognize the action of this factor.

2. Ionizing radiation can cause long-term consequences:

Malignant tumors

Shortening life

Decreased immunity.

3. Capable of penetrating deeply into the irradiated tissue.

4. Capable of total cumulative action.

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

3.1. Human exposure. Currently, penetrating radiation affects the human body as follows:

1. Causes external exposure human γ-rays from space, from the surface of the Earth, from building materials, from Chernobyl radionuclides.

2. 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 effects of ionizing radiation are not the direct cause of radiation sickness and human death. Really, The biological effects of ionizing radiation on a living organism are based on the chemical processes occurring in living cells after irradiation. Radioactive radiation cause ionization of atoms and molecules living tissues, resulting in breaking of normal molecular bonds And change in the chemical structure of cellular macromolecules. These changes entail either cell death or mutation.

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

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

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

2). Physicochemical properties of radionuclides - the position of elements in periodic table DI. Mendeleev, valence form of the radioisotope and 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 enter the body of animals and humans, as well as stable isotopes of elements, are eliminated as a result of exchange from the body with feces, urine, milk, eggs (chickens, geese) and other ways. There are:

a) Direct action- the molecule experiences changes directly from radiation when a photon or 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 may occur.

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 the migration of energy through the molecules of biopolymers, as a result of which the absorption of energy that occurs anywhere in the macromolecule leads to damage to its active center (for example, to the inactivation of an enzyme protein). In addition, not all energy transfer from an ionizing particle results in radiation damage. In explaining this paradox, they formulated principles of hitting and targets. According to these principles, cells have certain areas (targets), which, when hit, lead to damage. The radiation effect is caused by one or more ionizing particles entering the cell. Depending on how many hits on the target are necessary to defeat (one, two, etc.), objects are distinguished as single-impact, double-impact, etc. The principle of hits is applied most strictly to the analysis of damage to single-impact objects. In this case, ionizing radiation can cause:

- stochastic (rare) damage, There are no minimum doses for their appearance. As the dose is reduced, effects are still possible, but they become less likely. As the dose increases, it is not the severity of these effects that increases, but probability (risk) of their occurrence. The main stochastic consequences are cancer and hereditary genetic defects. The risk coefficients for their occurrence are presented in table. 7.1.