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GB/T 42142-2022: Analysis criterion for radiation source term in auxiliary and secondary coolant system 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 42142-2022 | English | 279 |
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Analysis criterion for radiation source term in auxiliary and secondary coolant system of pressurized water reactor nuclear power plant
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GB/T 42142-2022
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Basic data | Standard ID | GB/T 42142-2022 (GB/T42142-2022) | | Description (Translated English) | Analysis criterion for radiation source term in auxiliary and secondary coolant system of pressurized water reactor nuclear power plant | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F74 | | Classification of International Standard | 17.240 | | Word Count Estimation | 14,171 | | 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 42142-2022: Analysis criterion for radiation source term in auxiliary and secondary coolant system 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 17.240
CCSF74
National Standards of People's Republic of China
Auxiliary system and secondary circuit system of pressurized water reactor nuclear power plant
Radiation Source Term Analysis 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 1
5 General requirements 2
6 Analysis of Radiation Source Item of Auxiliary System 3
7 Secondary circuit system radiation source item 6
Appendix A (informative) Major nuclides and their classifications in the auxiliary system and secondary circuit system fluid of a typical PWR nuclear power plant 7
Appendix B (Informative) Estimation Parameter Table 8
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. Mao Yawei, Mi Aijun, Li Zhuoran, Wang Xiaoxia, Wang Bingheng, You Wei, Jing Chunning, Zhang Puzhong, Yang Defeng, Tian Yingnan,
Tang Shaohua, Lu Weifeng.
Auxiliary system and secondary circuit system of pressurized water reactor nuclear power plant
Radiation Source Term Analysis Guidelines
1 Scope
This document specifies the methods to be followed in the analysis of the radiation source items of the auxiliary system and the secondary circuit system of the pressurized water reactor nuclear power plant under normal operating conditions.
and assumptions.
This document is applicable to the analysis of the radiation source item of the auxiliary system and the secondary circuit system of the pressurized water reactor nuclear power plant under normal operating conditions.
2 Normative references
This document has no normative references.
3 Terms and Definitions
The following terms and definitions apply to this document.
3.1
normal operation
The operation of a nuclear power plant within specified operating limits and conditions.
3.2
Radiant source term sourceterm
The actual or possible release of radiation and (or) radioactive substances and
and energy related data.
Note. such as the type, quantity and chemical form of radionuclides.
3.3
auxiliary system auxiliarysystems
Support systems and related service systems for reactor coolant systems.
Note. Such as reactor pool, spent fuel pool cooling and processing system, chemical and volume control system, waste heat removal system and waste treatment system, etc.
4 general rules
4.1 The analysis of the radiation source item of the auxiliary system and the secondary circuit system is applicable to the auxiliary system and the secondary circuit system under the normal operating conditions of the PWR nuclear power plant.
System-related radiation safety analysis and shielding design.
4.2 When analyzing the radiation source item, the calculation and analysis shall be carried out based on the primary circuit design source item. The primary circuit design source item is based on the design basis source item (ie
The primary circuit fission product source item corresponding to the design basis cladding damage rate), the transient value of the main coolant radiation source item and the cold shutdown
peak.
4.3 The calculation of system and equipment source items should be based on the operating mode of the system, and the calculation model should be able to truly reflect the system function and process flow.
4.4 The process parameters should be selected according to the principle that the shielding design source term can envelop the different source terms that may occur under normal operating conditions.
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