GB/T 42292-2022Occupational exposure dose assessment of pressurized water reactor nuclear power plant (English PDF)
压水堆核电厂职业照射剂量评价
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Issued by
SAMR; SAC
Level / Type
National · Recommended
Issue date
December 30, 2022
Implementation date
July 1, 2023
Scope
GB/T 42292-2022 is the English-translated version of 压水堆核电厂职业照射剂量评价.
GB/T 42292-2022 is the Chinese national standard that sets the criteria and the methods for assessing the occupational exposure doses received at a pressurized water reactor nuclear power plant in operation.
It gives the general requirements, the general requirements for the assessment itself and the assessment methods, while informative appendices add the dosimetric and protection quantities used, a radiation risk diagram, the routine procedure for assessing committed internal doses by measurement, the activity categories used for collective dose, plant exposure statistics and the occupational exposure control process during operation.
It defines dose assessment, operational states and occupational exposure, and separates strongly penetrating radiation, such as neutrons, from weakly penetrating radiation such as alpha particles.
Clause 1 lets other plant types use it as a reference. Issued on 30 December 2022, applicable since 1 July 2023.
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Document preview — GB/T 42292-2022
National Standard of the People's Republic of China
- ICS
- 13.280
- Classification
- F 74
Issued by: State Administration for Market Regulation; Standardization Administration of the PRC
Contents
- Preface
- 1 Scope
- 2 Normative references
- 3 Terms and Definitions
- 4 General requirements
- 5 General Requirements for Occupational Exposure Dose Assessment
- 6 Methods for Occupational Exposure Dose Assessment
- Appendix B (Informative) Diagram of Radiation Risk Relationship
- Appendix C (informative) Routine procedures for assessing committed doses from internal exposure by measurement
- Appendix D (informative) Main activity categories for collective dose assessment of occupational exposure
- Appendix E (Informative) Statistics on Occupational Exposure Data of Nuclear Power Plants
- Appendix F (Informative) Schematic Diagram of External Exposure Dose Assessment of Nuclear Power Plant
- Appendix G (Informative) Occupational Exposure Control Process of Nuclear Power Plant Operation Stage
Foreword
This document is in accordance with the provisions of GB/T 1.1-2020 "Guidelines for Standardization Work Part 1: Structure and Drafting Rules for Standardization Documents" drafting.
1 Scope
This document specifies the criteria and methods for occupational exposure dose assessment of PWR nuclear power plant operating status.
This document is applicable to the occupational exposure dose assessment of PWR nuclear power plants in operation, and other types of nuclear power plants can be used as a reference.
2 Normative references
The contents of the following documents constitute the essential provisions of this document through normative references in the text. Among them, dated references For documents, only the version corresponding to the date is applicable to this document; for undated reference documents, the latest version (including all amendments) is applicable to this document.
GB/T 16148 Radionuclide Intake and Internal Exposure Dose Estimation Specification
GB 18871 Basic standards for protection against ionizing radiation and safety of radiation sources
GBZ 128 Specifications for Occupational External Exposure Personal Monitoring
GBZ 129 Personal monitoring specifications for occupational internal exposure
3 Terms and Definitions
The following terms and definitions apply to this document.
3.1 Dose assessment
Evaluating the acceptable and likely acceptable doses of ionizing radiation received by individuals or groups of people.
3.2 Operational states
The collective term for the two types of states, normal operation and anticipated operational event.
3.3 Occupational exposure
In addition to the exposure excluded by the relevant national regulations and standards and the practices or sources that are exempted according to the relevant national regulations and standards All exposures to which workers are exposed in the course of their work, in addition to their exposures.
3.4 Strong penetrating radiation
In a uniform and unidirectional radiation field, for a given orientation of the human body, if any small area of the skin receives an equivalent dose equal to If the effective dose ratio is less than 10 times, the radiation is called strong penetrating radiation.
Note: Strong penetrating radiation generally refers to the radiation of neutrons, electrons with energy higher than 2MeV and photons with energy higher than 15keV.
3.5 Weakly penetrating radiation
In a uniform and unidirectional radiation field, for a given orientation of the human body, if any small area of the skin receives an equivalent dose equal to If the effective dose ratio is greater than 10 times, the radiation is called weakly penetrating radiation.
Note: Weak penetrating radiation generally refers to electrons with energy lower than 2MeV (such as low-energy beta/beta-, internal conversion electrons), protons, photons with energy lower than 15keV and Radiation from massive charged particles such as alpha particles.
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This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 19 pages — is available in the English PDF.
Referenced standards
Normative references
- GB/T 16148Method of estimation for the intake and internal dose of radionuclides
- GB 18871Basic Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources
- GBZ 128Course development guide for education about standardization - Fundamentals of quality management
- GBZ 129Surface chemical analysis - Electron spectroscopies - Measurement of the thickness and composition of nanoparticle coatings
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Related Standards
GB 18871-2002 — Basic Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources
GB/T 16148-2009 — Specification for assessments of intakes and internal doses of radionuclides
GB/T 16148-2026 — Method of estimation for the intake and internal dose of radionuclides
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