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Jensen, S.E.; Kayser, W.V.; Worley, L.C.; Yates, J.; Pugh, R.A.
Exxon Nuclear Co., Richland, Wash. (USA)1975
Exxon Nuclear Co., Richland, Wash. (USA)1975
AbstractAbstract
[en] The document is presented as a demonstration of the WREM/ENC calculational procedure using a Combustion Engineering Plant of the Palisades type. The calculational procedures used are in accordance with the ENC PWR evaluation model as described in XN-75-41, Volumes I and II and supplements, including Supplement 7 which describes the current analytical models. The loss-of-coolant accident investigated was a split configuration with a break area equal to twice the pipe cross-sectional area. The break was assumed to occur in one cold leg or pump discharge pipe. This investigation involved calculations using the following primary WREM/ENC codes: RELAP-EM for blowdown and hot channel analysis, TOODEE2 for hot channel during refill and reflood, and RELAP4-EM FLOOD for core reflood analysis. The document includes descriptions of all portions of the loss-of-coolant analysis. Principal results of these analyses are presented, including peak clad temperatures, metal/water reaction percentages, and transient time sequences for major events
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7 Dec 1975; 62 p; Exxon Nuclear Co., Richland, WA
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