核电厂操纵员认知行为失误分析

核电厂是一个集机械、电子、自动控制的复杂人机系统,它要求操纵员具有良好的认知能力,能够进行正确的分析和操作。文章对操纵员在核电厂事故状态下的认知行为进行探讨。将认知行为过程分为5个阶段,并应用认知行为模型对操纵员认知过程中的失误情况进行了分析,得到操纵员发生认知失误的阶段和根源,从而为核电厂设备的人机界面设计和操纵员的培训与评价提供相应的依据。     

核电厂数字化主控室操纵员行为形成因子评价模型

由于人因可靠性分析(HRA)方法中用于量化基本人因失误概率(HEP)的行为形成因子（PSF）数目众多,且一般是通过专家评判,从而带有主观性、模糊性和不确定性。本文提出一种利用相关系数矩阵、图的距离分类和主成分分析法相结合的方法构建核电厂数字化主控室操纵员PSF的评价模型,其目的是识别不同类型的人因事件中主要影响人因绩效的PSF,以供决策减少人因失误。对某核电厂的179起人因事件报告进行实验,结果表明该评价模型能对核电厂数字化主控室操纵员的PSF进行有效评价。     

Recent Training Technology of BWR Operators Using Full Scope Simulators

Nuclear power plants are being operated at high standards now in Japan. There are far few opportunities for operators to perform in challenging situations. To maintain skill and refinement, the simulator training is indispensable for them.

BWR Operator Training Center (BTC) provides training courses according to the grade and duty of the operators. The training force constitutes of personnel from utilities', manufacturers' and also BTC-hired personnel.

One of the big features of BTC training is composite team type. In this form of training, men from different plants make a team and help each other study.

On the human factor viewpoint, error experience on simulators is one of the important items. Training on recognizing subtle symptom is an example of a recent development. Team training for actual crew is effective from various viewpoints.     

Application and In-depth Assessment of RETRAN-3D for Best Estimate Analysis of Nuclear Power Plant Transients

The code RETRAN-3D has been extensively applied in the project STARS at PSI to perform BE analysis for a range of operational and other (non-LOCA) transients for the Swiss NPPs, which include both PWRs and BWRs. Extensive assessment employing experimental and plant data has provided confidence in the applicability and accuracy of RETRAN-3D for the analysis of transients in both types of LWRs. In this context, this paper presents an in-depth study of the performance of the code for two types of applications. First, a detailed analysis of BWR/6 recirculation pump trip tests shows that the code is able to accurately predict the coupled neutronic and thermal-hydraulic behaviour during an operational transient in which plant-specific system features (e.g. SRI insertion, response of the recirculation line valves to changes in flow, etc.) play an important role. Second, RETRAN-3D is applied to BE analysis of a PWR beyond-design basis scenario, namely the failure of the RHR system during reactor shutdown. In-depth assessment of the results obtained demonstrates the applicability of RETRAN-3D and the need for employing a BE approach to predict a more accurate, shorter “time window” for operator remedial action than that estimated using the assumption of uniform primary temperature distribution.