scholarly journals Evaluation of MONJU Core Damage Risk with Change of AOT Using Probabilistic Method

2010 ◽  
Vol 4 (1) ◽  
pp. 84-93
Author(s):  
Masutake SOTSU ◽  
Kenichi KURISAKA
Keyword(s):  
Probabilistic Method ◽  
Core Damage ◽  
Damage Risk

Evaluation of Monju Core Damage Risk With Change of AOT Using Probabilistic Method

2009 ◽  
Author(s):  
Masutake Sotsu ◽  
Kenichi Kurisaka
Keyword(s):  
Probabilistic Method ◽  
Fast Breeder Reactor ◽  
Core Damage ◽  
Safety Regulations ◽  
Cooling Loops ◽  
Damage Risk

MONJU is a sodium-cooled, loop-type prototype fast breeder reactor with three primary cooling loops which can supply 280 MW of electricity. Limiting conditions of operation (LCO) defined in the safety regulations in MONJU given the allowed outage time (AOT) are evaluated using a PSA technique. The result indicates the possibility of limit extension and some prospects that we should examine.

scholarly journals Evaluation of MONJU Core Damage Risk due to Control Rod Function Failure

2012 ◽  
Vol 6 (3) ◽  
pp. 462-471
Author(s):  
Masutake SOTSU ◽  
Kenichi KURISAKA
Keyword(s):  
Control Rod ◽  
Core Damage ◽  
Rod Function ◽  
Damage Risk

Discussion on Application of Accident Sequence Precursor Analysis in China

2017 ◽  
Author(s):  
Jiang Hu ◽  
Guoxu Zhang ◽  
Yushu Zhang ◽  
Binbin Zhang ◽  
Zhi Xiao
Keyword(s):  
Nuclear Power ◽  
Reactor Core ◽  
Operating Experience ◽  
Evaluation Process ◽  
Management Platform ◽  
Core Damage ◽  
Current State ◽  
Core Cooling ◽  
Damage Risk ◽  
Degraded Condition

An accident sequence precursor (ASP) is an initiating event or degraded condition that, when coupled with one or more postulated events, could result in inadequate core cooling or even severe reactor core damage. Through the systematical investigation and evaluation of nuclear power plant (NPP) operating experience, the ASP analysis could provide a comprehensive, risk-informed view of NPP operating experience, a measure for trending core damage risk, a partial validation of the current state of practice in risk assessment, and also a feedback to regulatory activities. This paper firstly gives a brief review on the ASP evaluation process of U.S. and German, and then introduces the current progresses on the establishment of ASP regulatory framework and the development of ASP management platform, which are carrying out by the related nuclear regulation agency in China. Also, this paper gives some insightful discussions on issues such as the ASP application and problems maybe faced.

Sensitivity Analyses of Steam Generator Tube Thickness on Induced-SGTR in SBO Accident

2013 ◽  
Vol 341-342 ◽  
pp. 1338-1341
Author(s):  
Jin Rong Qiu ◽  
Chang Hong Peng ◽  
Yun Guo
Keyword(s):  
Steam Generator ◽  
Nuclear Power ◽  
Fission Products ◽  
Sensitivity Analyses ◽  
Steam Generator Tube ◽  
Core Damage ◽  
Reference Plant ◽  
Station Blackout ◽  
Level I ◽  
Damage Risk

For nuclear power plant, station black-out (SBO) is the events that contribute significantly to the level-I core damage risk. For an SBO, it is assumed that both the off-site power and on-site diesel generators fail to supply alternating-current power for the plant systems. SBO induced steam generator tube rupture (SGTR) is a concern because the steam generator (SG) tubes are parts of the reactor coolant pressure boundary and failure of the SG tubes may lead to fission products bypassing the containment. The SG tube integrity may be challenged by high temperature and high pressure conditions and may have a potential to fail due to creep rupture. This study focuses on the probability of SBO induced SGTR accidents under the station blackout (SBO) with RCS integrity, seal LOCA and steam relief valves remaining stuck open for the reference plant. At last, the sensitivity of the tube thick is studied.

Transformation of classical PSA and DSA into the form of conditional event tree: An approach of human action in time dependent core damage risk

2022 ◽  
Vol 165 ◽  
pp. 108662
Author(s):  
Alireza Najafi ◽  
Athena Shahsavand ◽  
Seyed Ali Hosseini ◽  
Amir Saeed Shirani ◽  
Faramarz Yousefpour ◽  
...  
Keyword(s):  
Human Action ◽  
Time Dependent ◽  
Event Tree ◽  
Conditional Event ◽  
Core Damage ◽  
Damage Risk

Damage Risk: An Evaluation of the Effects of Exposure to 85 versus 90 dBA of Noise

1976 ◽  
Vol 19 (2) ◽  
pp. 216-224 ◽  
Author(s):  
James T. Yates ◽  
Jerry D. Ramsey ◽  
Jay W. Holland
Keyword(s):  
White Noise ◽  
Statistical Difference ◽  
Noise Exposure ◽  
Threshold Shift ◽  
Temporary Threshold Shift ◽  
Noise Levels ◽  
Potential Damage ◽  
Full Day ◽  
Damage Risk

The purpose of this study was to compare the damage risk of 85 and 90 dBA of white noise for equivalent full-day exposures. The damage risk of the two noise levels was determined by comparing the temporary threshold shift (TTS) of 12 subjects exposed to either 85 or 90 dBA of white noise for equivalent half- and full-day exposures. TTS was determined by comparing the pre- and postexposure binaural audiograms of each subject at 1, 2, 3, 4, 6, and 8 kHz. It was concluded that the potential damage risk, that is, hazardous effect, of 90 dBA is greater than 85 dBA of noise for equivalent full-day exposures. The statistical difference between the overall effects of equivalent exposures to 85 dBA as compared to 90 dBA of noise could not be traced to any one frequency. The damage risk of a full-day exposure to 85 dBA is equivalent to that of a half-day exposure to 90 dBA of noise. Within the limits of this study, TTS t was as effective as TTS 2 for estimating the damage risk of noise exposure.

DEFINITION OF TIME SPENT ON REPAIR OF BUS TRANSMISSION UNITS TAKING INTO ACCOUNT TECHNOLOGICAL EQUIPMENT RELIABILITY

2020 ◽  
Vol 2020 (9) ◽  
pp. 29-33
Author(s):  
Sergey Bulatov
Keyword(s):  
Negative Impact ◽  
Probabilistic Method ◽  
Technological Equipment ◽  
Quality And Safety ◽  
Transmission Unit ◽  
Equipment Reliability ◽  
Hours Of Work ◽  
Definition Of ◽  
Time Decrease

The paper purpose is the effectiveness estimation in the technological equipment use, taking into account its reliability and productivity for defective transmission units of buses. The problem consists in the determination of time to be spent on repair of bus transmission units taking into account technological equipment reliability. In the paper there is used a probabilistic method for the prediction bus transmission units, and also a method of the dynamics of averages which allow ensuring minimum of costs for units downtime during repair and equipment cost. The need for repair of transmission units (gear box) arises on an average after 650 hours, the average productivity of the bench makes 4.2 bus / hour. The bench fails on the average after 4600 hours of work, the average time of the bench makes 2 hours. In such a way the solution of the problem specified allows analyzing the necessity of time decrease for transmission unit repair to avoid long downtimes of buses in repair areas without negative impact upon high repair quality and safety during the further operation.

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