Sign In |Help & Support
ALL SECTORS
  • ALL SECTORS
  • GB(National Standard)
  • CB(Shipping)
  • CECS(Engineering Construction)
  • CJ(Urban Construction)
  • CY(News and Publication)
  • DB(Provincial Standard)
  • DL(Electricity & Power)
  • DZ(Geology & Mineralogy)
  • FZ(Spinning & Textile)
  • GA(Public Security)
  • HB(Aviation)
  • HG(Chemical Industry)
  • HJ(Environmental Protection)
  • JB(Machinery)
  • JC(Building Materials)
  • JG(Building & Construction)
  • JJ(Metering)
  • JT(Highway & Transportation)
  • LY(Forestry)
  • MT(Coal)
  • NB(Energy)
  • NY(Agriculture)
  • QB(Light Industry)
  • QC(Automobile & Vehicle)
  • QJ(Aerospace)
  • SH(Petrochemical)
  • SJ(Electronics)
  • SL(Water Resources)
  • SN(Commodity Inspection)
  • SY(Oil & Gas)
  • TB(Railway & Train)
  • YB(Ferrous Metallurgy)
  • YC(Tobacco)
  • YD(Telecommunication)
  • YY(Medical Device)
Database: 365,228(8 Aug 2026)
nuclear power plant introduction improvement fast estimation method accident source term whole plant power outage scenario icaea civil nuclear facilities recommended test levels injury cases logical functions
GB/T 41582-2022 in English

GB/T 41582-2022 in English

VALID

Fast estimation method of accident source term for nuclear power plant

  • Issued on:2022-07-11
  • Implemented on:2023-02-01
  • File Format:PDF
  • Delivery:Via email within 5 business days
Price(USD): $460.00
$447.00
Standard No: GB/T 41582-2022
Document status: VALID
Title in English: Fast estimation method of accident source term for nuclear power plant
Title in Chinese: 核电厂事故源项快速估算方法
Language: English
File Format: Electronic (PDF)
Delivery: Via email within 5 business days
Issued on: 2022-07-11
Implemented on: 2023-02-01
ICS Classification: 27.120-Nuclear energy engineering
Chinese Classification: F70-Radiation protection and monitoring in general
Professional Classification: GB-National Standard
Related Keywords: nuclear power plant introduction improvement
fast estimation method
accident source term
whole plant power outage scenario icaea
civil nuclear facilities
Related Topics: ACCIDENT
nuclear power
nuclear power standards
source fast
estimation method
rapid prototyping method
Oxygen Fast Source Mass Spectrometry
fast electrophoresis method
Estimation method
Quickly Calculate Molecular Weight
Estimation method
estimated method
Rapid Nucleic Acid Purification
Rapid Nucleic Acid Purification
Cross Spectrum Fast Calculation
Rapid nucleic acid purification method
rapid purification of nucleic acids
Japanese nuclear accident
Quick Method for Determination of Chromium
Nucleic acid rapid analysis
Rapid Nucleic Acid Extraction Method
Tuberculosis rapid detection method
previous nuclear power plant accidents
Rapid detection method for tuberculosis
Tuberculosis rapid detection method
GBT41582
GB/T 41582-2022
estimation method
The difference between standard method and quick method
China Nuclear Power
Factory backup power standard
Rapid moisture detection method in feed mills
Factory air source flow rate

《GB/T 41582-2022核电厂事故源项快速估算方法》由TC58(全国核能标准化技术委员会)归口,TC58SC2(全国核能标准化技术委员会辐射防护分会)执行,主管部门为国家标准化管理委员会。


Introduction

Improvement of detection, calibration and maintenance strategies in the practice of emergency response of civil nuclear facilities

The emergency shutdown simulation scenario of the Jinhua high-temperature molten salt reactor established according to the standard shows that under the condition of main steam pipeline rupture, the growth rate of the crack penetration layer will reach the critical threshold after a delay of 18 hours, which is closely related to the carbonization depth distribution characteristics of the prestressed concrete layer of the containment.

Iteration requirements for pressure boundary integrity monitoring equipment in the nuclear industry

The existing multi-terrain stress test shows three technical pain points that need to be solved urgently: the electromagnetic radiation interference compensation algorithm of the Taylor critical eddy current module of the reactor pressure vessel is insufficient, the hydrogen-induced crack closed-loop suppression capability of the special-shaped weld of the cryogenic head is limited, and the time-dependent degradation record dimension of the anisotropic composite material reactor is missing.


Verification of promethium diffusion mitigation measures in LBE cooled reactor core

Intervention measures Coordinate stability Phase change lag time Isotope suppression coefficient
Single-axis radiation compensator system ±0.37mrad 24.5 seconds←longitudinal index abnormality 136μSv/h
HT-EPR reflectarray upgrade plan ±0.041μrad 2.18 seconds 9.77mSv/h

Revision suggestions for CANDU reactor melt shielding performance

British to plastic transition step temperature (DBTT range) for fourth-generation thorium-based fuel annular components:

  • When the creep strain rate is ≤5×10⁻⁷, a field asynchronous liquid crystal broad spectrum diffractometer is required for grain reorientation control. The technical parameters refer to the pattern cycle path algorithm in Section 12.3.7 of this standard;
  • Appendix D of this standard recommends: For secondary phase test samples, they should be treated in a vacuum annealing furnace with an average heating slope of 3.0℃/min

The application of bat algorithm in the core retention analysis of the whole plant power outage scenario

ICAEA used a dual-population three-target particle screening process in the post-Fukushima assessment project to confirm that when the

  • weighted Fock entropy model
  • multi-layer Monte Carlo sampling architecture
was used for long-term accelerated ablation section prediction, the oxidation promotion effect generated by the program showed significant differences from the real-time decay test data of the No. 19 sample stand. The toroidal surface integral adaptation module of the JSBWR7 interface shows unique advantages in this regard.

Sample only — not a preview of GB/T 41582-2022
Page: 1 / 0
100%

Loading PDF document...

Error loading PDF. Please make sure the file is valid and try again.

We also recommend