GB/T 42141-2022Radiation protection design criterion for nuclear island building under accident condition of presssurized water reactor nuclear power plant (English PDF)
压水堆核电厂事故工况核岛厂房辐射防护设计准则
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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 42141-2022 is the English-translated version of 压水堆核电厂事故工况核岛厂房辐射防护设计准则.
GB/T 42141-2022 sets the principles, methods and assumptions for designing radiation protection in the nuclear island buildings of a pressurised water reactor plant under accident conditions.
It covers the accident source term, the radiation protection that keeps plant workers safe while they carry out emergency tasks, the radiation environment conditions equipment and instruments must withstand, the radiation zoning that applies under accident conditions and the setting of alarm thresholds for radiation monitoring instruments, with informative appendices on the removal effect of the containment spray system and on the element fractions released into the containment.
Its definitions separate design basis accidents, divided into rare and extreme accidents, from severe accidents. Clause 1 applies it to pressurised water reactors, with other reactor types taking it as a reference. Issued on 30 December 2022, it has applied since 1 July 2023.
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Document preview — GB/T 42141-2022
National Standard of the People's Republic of China
- ICS
- 13.280
- Classification
- F 72
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
- 5 Accident condition source item
- 6 Radiation protection based on the safety of workers in the plant during accident conditions
- 7 Radiation environmental conditions of equipment and instruments in the plant during accident conditions
- 8 Radiation division 5 under accident conditions
- 9 Determination of alarm thresholds for radiation monitoring instruments in accident conditions
- Appendix A (Informative) Removal Effects of Containment Spray System
- Appendix B (informative) The share of each element released into the containment vessel
- Appendix C (Informative) Fraction of Elements Released from Fuel into Containment Vessel During Accident
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 radiation protection design, equipment and instruments for the safety radiation protection of nuclear island building staff in pressurized water reactor nuclear power plants under accident conditions.
Principles, methods and assumptions to be followed in terms of radiation environment requirements, radiation partitions under accident conditions, and monitoring instrument thresholds.
This document is applicable to the radiation protection design of the nuclear island building under the accident condition of the pressurized water reactor nuclear power plant, and other reactor types shall be implemented by 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 18871-2002 Basic standards for protection against ionizing radiation and safety of radiation sources
3 Terms and Definitions
The following terms and definitions apply to this document.
3.1 Accident condition
Deviation from normal operation, a condition in which the frequency of occurrence of operational events is less than expected but more serious.
Note: Accident conditions include design basis accidents and design extension conditions. Design extension conditions include conditions without significant core damage and core meltdown (severe accident) conditions.
3.2 Design basis accident
A hypothetical accident leading to accident conditions in a nuclear power plant.
Note 1. The release of radioactive material in these accidents is within the specified limits, and the nuclear power plant is designed according to established design criteria and conservative methods.
Note 2. According to the frequency of accidents, design basis accidents are divided into two types. rare accidents and extreme accidents.
3.3 Serious accident severe accident
Accident conditions whose severity exceeds the design basis accident and causes significant deterioration of the core.
3.4 Under accident conditions, in order to complete
the emergency response tasks, the staff need to enter or stay in the key areas with high radiation levels in the plant. area.
Note: The radiation protection design of key areas meets all relevant requirements to ensure the radiation safety of personnel in completing emergency tasks.
3.5 radiation environmental conditions
Under accident conditions, the dose rate level of the environment where the equipment and instruments are located, and the cumulative radiation received during the time limit for performing safety functions
......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 15 pages — is available in the English PDF.
Referenced standards
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