BEACON/MOD2A analysis of the Arkansas-1 reactor cavity during a hypothetical hot leg break
Description
As part of the evaluation of the new MOD2A version of the BEACON code, the Arkansas-1 reactor cavity was modeled during a hypothetical loss-of-coolant accident. Results of the BEACON analysis were compared with results obtained previously with the COMPARE containment code. Studies were also made investigating some of the BEACON interphasic, timestep control, and wall heat transfer options to assure that these models were working properly and to observe their effects on the results. Descriptions of the Arkansas-1 reactor cavity, initial assumptions during the hypothetical LOCA, and methods of modeling with BEACON are presented. Some of the problems encountered in accurately modeling the penetrations surrounding the hot and cold leg pipes are also discussed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 43 p.
- Report number
- CDAP-TR--046
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10473252
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ARKANSAS-1 REACTOR; B CODES; CONTAINMENT BUILDINGS; LOSS OF COOLANT; MATHEMATICAL MODELS; PRESSURE GRADIENTS; PRESSURE VESSELS; REACTOR SAFETY; STRESSES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONTAINMENT; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS