Assessing the uncertainties in reactor accident consequences by means of RSM: The case of an ATWS in a PWR-Reference-Cited by-同舟云学术

Assessing the uncertainties in reactor accident consequences by means of RSM: The case of an ATWS in a PWR

Published:1985-09 Issue:2 Volume:88 Page:179-194
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Cacciabue P.C.,Olivi L.,Parisi P.,Brunelli F.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference20 articles.

1. Research project 309;Mazumdar,1975

2. RSM modelling of an ATWS accident simulated by the ALMOD code: methodological and practical achievements;Olivi;EUR Report 9449EN,1984

3. Uncertainty in calculated surface temperature and surface heat flux of THTF heater rods;Childs;NUREG/CR-1211,1980

4. Uncertainty analysis for a PWE loss-of-coolant accident: II. alternative core damage estimators;Berman;NUREG/CR-1364,1980

5. Accident mechanisms modelled by RSM for safety assessment on the plants;Brunelli,1984

Cited by 6 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Strength assessment of SMART design against anticipated transient without scram;Progress in Nuclear Energy;2015-11

2. Response surface approximation of a fire risk analysis computer code;Reliability Engineering & System Safety;1990-01

3. Limiter probabilistic lifetime analysis;Fusion Engineering and Design;1988-01

4. Accident sequence dynamic simulation versus event trees;Reliability Engineering & System Safety;1988-01

5. Dynamic Logical Analytical Methodology Versus Fault Tree: The Case Study of the Auxiliary Feedwater System of a Nuclear Power Plant;Nuclear Technology;1986-08