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GB/T 41591-2022: Initial criticality tests for pressurized water reactor of nuclear power plants
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Initial criticality tests for pressurized water reactor of nuclear power plants
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GB/T 41591-2022
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Basic data | Standard ID | GB/T 41591-2022 (GB/T41591-2022) | | Description (Translated English) | Initial criticality tests for pressurized water reactor of nuclear power plants | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F63 | | Word Count Estimation | 8,814 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 41591-2022: Initial criticality tests for pressurized water reactor of nuclear power plants---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.
Initial criticality tests for pressurized water reactor of nuclear power plants
ICS 27.120.20
CCSF63
National Standards of People's Republic of China
The first criticality test of a pressurized water reactor nuclear power plant reactor
Published on 2022-07-11
2023-02-01 Implementation
State Administration for Market Regulation
Released by the National Standardization Administration
directory
Preface III
1 Scope 1
2 Normative references 1
3 Terms and Definitions 1
4 Test purpose 2
5 Test initial conditions 2
6 Test method 2
6.1 Method overview 2
6.2 The first critical 2
6.3 Verification of linearity and overlap of the ex-reactor nuclear instrumentation system 3
6.4 Determining the neutron fluence rate range for zero-power physical experiments 3
6.5 Calibrating the Reactivity Meter 4
7 Notes 4
8 Acceptance Criteria 4
9 Test records and reports 4
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 of Standardization Documents"
drafted.
Please note that some content of this document may be patented. 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 General Nuclear Power Engineering Co., Ltd., Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Sanmen Nuclear Power Co., Ltd.
The main drafters of this document. Li Junde, Zhang Songwen, Li Wenshuang, Hao Tengfei, Zhao Yuntao, Yi Yi, Yang Wenqing.
The first criticality test of a pressurized water reactor nuclear power plant reactor
1 Scope
This document specifies the test purpose, initial conditions, test methods, precautions, and acceptance of the first criticality test of a pressurized water reactor nuclear power plant.
Guidelines, and requirements for test records and reports.
This document applies to the first criticality test of the reactor during the commissioning phase of a new pressurized water reactor nuclear power plant.
2 Normative references
The contents of the following documents constitute essential provisions of this document through normative references in the text. Among them, dated citations
documents, only the version corresponding to that date applies to this document; for undated references, the latest edition (including all amendments) applies to
this document.
NB/T.20145 Nuclear power plant commissioning test procedures and report writing specifications
3 Terms and Definitions
The following terms and definitions apply to this document.
3.1
The inverse of the ratio of the current neutron count rate to the base count rate.
Calculate according to formula (1).
ICRR=C0/C(1)
where.
C0---base count rate;
C --- Current neutron count rate.
3.2
reactive reactivity
A parameter that characterizes the degree to which a chain nuclear fission reaction medium or system deviates from criticality.
3.3
doubleperiod
The time required for the neutron fluence rate in the reactor to change exponentially by a factor of 1.
3.4
startup rate
A physical quantity that characterizes the rate of change of the neutron fluence rate in a reactor.
Note. The starting rate is in DPM (DecadesPerMinute), and 1DPM means that the neutron fluence rate increases 10 times per minute according to an exponential law.
3.5
starting interval startinginterval
An interval of predicted primary coolant boron concentration before the reactor reaches criticality.
Note. Considering factors such as calculation error, measurement error and uncertainty, the reactor may enter a critical state at any time during the start-up interval.
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