GB/T 41591-2022 in English
VALIDInitial 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
$156.00
《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
| Control item | Liquid dilution control method | Gas dilution control method |
|---|---|---|
| Critical extrapolation method | Real-time ICRR calculation(countdown rate) | Four-point linear countdown correction |
| Applicable scenarios | Typical large-scale power station | Regional small experimental reactor | < /tr>
| Operation cycle | ≥72 hours continuous monitoring | Segmented 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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