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pressurized water reactor reactor criticality test standardsnational standard gb/t41591-2022 nuclear power plants introductionoverview initial criticality tests nuclear power plant brick masonry members cokl drawn superalloy bars down hole drilling tools
GB/T 41591-2022 in English

GB/T 41591-2022 in English

VALID

Initial criticality tests for pressurized water reactor of nuclear power plants

  • Issued on:2022-07-11
  • Implemented on:2023-02-01
  • File Format:PDF
  • Delivery:Via email within 1~3 business days
Price(USD): $160.00
$156.00
Standard No: GB/T 41591-2022
Document status: VALID
Title in English: Initial criticality tests for pressurized water reactor of nuclear power plants
Title in Chinese: 压水堆核电厂反应堆首次临界试验
Language: English
File Format: Electronic (PDF)
Delivery: Via email within 1~3 business days
Issued on: 2022-07-11
Implemented on: 2023-02-01
ICS Classification: 27.120.20-Nuclear power plants. Safety
Chinese Classification: F63-Power reactor
Professional Classification: GB-National Standard
Related Keywords: pressurized water reactor
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nuclear power plant
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GB/T 41591-2022
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Pressurized Water Reactor Standard

《GB/T 41591-2022压水堆核电厂反应堆首次临界试验》由TC58(全国核能标准化技术委员会)归口,TC58SC3(全国核能标准化技术委员会反应堆技术分会)执行,主管部门为国家标准化管理委员会。


Introduction

Overview of Reactor Criticality Test Standards

National standard GB/T41591-2022 clarifies the system verification requirements for the first controlled chain reaction of a pressurized water reactor nuclear power plant, including the establishment of specifications for six major types of test initial conditions, and specifies the operating boundaries of the two start-up modes of rod dilution. The standard focuses on controlling the joint test process of the source range detection system and the reactivity instrument.


Analysis of key technical links

< /tr>
Control itemLiquid dilution control methodGas dilution control method
Critical extrapolation methodReal-time ICRR calculation(countdown rate)Four-point linear countdown correction
Applicable scenariosTypical large-scale power stationRegional small experimental reactor
Operation cycle≥72 hours continuous monitoringSegmented operation mode

Key operation assessment indicators

Chapter 8.4 Establish the accuracy requirements of the nuclear critical modulus: The relative deviation between the reactivity measurement value (ρF) and the doubling period estimated value (ρD) must be continuously stable within the range of ±4%. Under abnormal conditions, the unit must trigger the second-level protection setting.


Implementation of the recommended system

  • System calibration preset: Complete the source range channel and DCS system 72 hours before the test
  • Graded monitoring mechanism: Acute nuclear dose changes trigger secondary condition assessment
  • Digital archives: The commissioning report strictly follows the NB/T20145 chapter model

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