Modeling and measuring the effects of imprecision in accident management

Annals of Nuclear Energy

Volumn 29, Issue 7, 2002, Pages 821-833

  Yu, Donghan ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; COMPUTER SIMULATION; FUZZY SETS; MONTE CARLO METHODS; PROBABILITY;

ACCIDENT MANAGEMENT STRATEGIES;

NUCLEAR REACTOR ACCIDENTS;

EID: 0036568005     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(01)00077-9     Document Type: Article

References (9)

1. A subjective approach for ranking fuzzy numbers
2. Vertex method for computing functions of fuzzy variables
3. Uncertainty and sensitivity analysis techniques for use in performance assessment for radioactive waste disposal
4. When to separate uncertainties and when not to separate
5. An application of fuzzy concepts to modeling of reliability analysis
6. A procedure for ordering fuzzy subsets of the unit interval
7. Evaluation of a severe accident management strategy for BWRs: Drywell flooding
8. Use of an influence diagram and fuzzy probability for evaluating accident management in a BWR