This paper outlines a University of Tennessee indepen dent study of the safety and reliability of the Clinch River Breeder Reactor Plant in Oakridge, Tennessee. The study uses several kinds of models, and analytical computer pro grams, one of which (BACFIRE) is briefly described and illustrated.
Get full access to this article
View all access options for this article.
References
1.
Baloh, F.J.Brown, N.W.Graham, J.Smith, A.M.Zemanick, P.P.Clinch River Breeder Reactor Plant System ReliabilityIEEE Transactions on Reliability vol. R-24 No. 4 August 1976
2.
Burdick, G.R. et al. COMCAN - a Computer Program for Common Cause Analysis ANCR-1314 June 1976
3.
4.
Esary, J.D.Ziehms, H.Reliability Analysis of Phased Missions Reliability and Fault Tree AnalysisSIAM1975 pp. 213-236
5.
Fussell, J.B.Rasmuson, D.M.Wilson , J.R.Burdick, G.R.Zipperer, J.C.A Collection of Methods for Reliability and Safety Engineering ANCR-1273Idaho National Engineering LaboratoryIdaho Falls, Idaho April 1976
6.
Fussell, J.B.Fault Tree Anolysis - Concepts and Techniques NATO Advanced Study Institute on Generic Techniques of System Reliability AssessmentNordhoff Publishing Company1976 Available from author
7.
Fussell, J.B.Henry, E.B.Marshall , N.H.MOCUS - a Computer Program to Obtain Minimal Sets from Fault Trees ANCR-1156Idaho National Engineering LaboratoryIdaho Falls, Idaho August 1974
8.
Graham, J.Strawbridge, L.E.Brad-Bury, P.Safety of the Clinch River PlantNuclear Engineering International vol. 19 no. 221 October 1974 pp.854-857
9.
10.
Reactor Safety Study WASH-1400U.S. Nuclear Regulatory CommissionWashington, D.C. October 1975
11.
Vesly, W.E.Narum, R.E.PREP and KITT: Computer Codes for the Automatic Evaluation of a Fault Tree IN-1349 August 1970
