Published October 2, 1975 | Version v1
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WREM-based generic PWR ECCS evaluation model. 3-loop Westinghouse large break example problem (using September 26, 1975 model)

Description

Appendix D is presented as a demonstration of the WREM/ENC calculational procedure using a typical Westinghouse three-loop NSSS. 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 5, Revision 1 (the September 26, 1975, model). The loss-of-coolant accident investigated was a double-ended guillotine cold leg break. Three analyses are presented which include discharge coefficients (C/sub D/) of 1.0, 0.6 and 0.4. The investigation involved calculations using the following primary WREM/ENC codes: RELAP4-EM for blowdown and hot channel analysis, TOODEE2 for hot channel during refill and reflood, and RELAP4-EM FLOOD for core reflood analysis. This appendix includes descriptions of all portions of the loss-of-coolant analysis with example problem input. Principal results of these analyses are contained in Tables. These results include peak clad temperatures and metal/water reaction percentages. Also included are summaries of the transient time sequences for major events. All salient results from the three analyses are presented in graphical form

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
145 p.
Report number
XN--75-41(Vol.2)(App.D)

Optional Information

Notes
Exxon Nuclear Co., Inc., Richland, WA.