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GB/T 42141-2022: Radiation protection design criterion for nuclear island building under accident condition of pressurized water reactor nuclear power plant
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| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB/T 42141-2022 | English | 279 |
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Radiation protection design criterion for nuclear island building under accident condition of pressurized water reactor nuclear power plant
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GB/T 42141-2022
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Basic data | Standard ID | GB/T 42141-2022 (GB/T42141-2022) | | Description (Translated English) | Radiation protection design criterion for nuclear island building under accident condition of pressurized water reactor nuclear power plant | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F72 | | Classification of International Standard | 13.280 | | Word Count Estimation | 14,131 | | Date of Issue | 2022-12-30 | | Date of Implementation | 2023-07-01 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 42141-2022: Radiation protection design criterion for nuclear island building under accident condition of pressurized water reactor nuclear power plant
---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
ICS 13.280
CCSF72
National Standards of People's Republic of China
Accident conditions of PWR nuclear power plant Nuclear island building
Radiation Protection Design Guidelines
Posted on 2022-12-30
2023-07-01 implementation
State Administration for Market Regulation
Released by the National Standardization Management Committee
table of contents
Preface III
1 Scope 1
2 Normative references 1
3 Terms and Definitions 1
4 General 2
5 Accident condition source item 2
6 Radiation protection based on the safety of workers in the plant during accident conditions3
7 Radiation environmental conditions of equipment and instruments in the plant during accident conditions 4
8 Radiation division 5 under accident conditions
9 Determination of alarm thresholds for radiation monitoring instruments in accident conditions5
Appendix A (Informative) Removal Effects of Containment Spray System 6
Appendix B (informative) The share of each element released into the containment vessel7
Appendix C (Informative) Fraction of Elements Released from Fuel into Containment Vessel During Accident8
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.
Please note that some contents of this document may refer to patents. The issuing agency of this document assumes no responsibility for identifying patents.
This document is proposed and managed by the National Nuclear Energy Standardization Technical Committee (SAC/TC58).
This document is drafted by. China Nuclear Power Engineering Co., Ltd., China Guangdong Nuclear Power Engineering Co., Ltd.
The main drafters of this document. Jing Chunning, Mao Yawei, Mi Aijun, You Wei, Qiu Lin, Wang Xiaoxia, Wang Bingheng, Pan Yuelong, Xiong Jun.
Accident conditions of PWR nuclear power plant Nuclear island building
Radiation Protection Design Guidelines
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 designbasisaccident
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
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
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