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Title: Evaluation of COBRA III-C and SABRE-I (wire wrap version) computational results by comparison with steady-state data from a 19-pin internally guard heated sodium cooled bundle with a six-channel central blockage (THORS bundle 3C). [LMFBR]

Conference ·
OSTI ID:5904005

The predicted computational results of two well-known sub-channel analysis codes, COBRA-III-C and SABRE-I (wire wrap version), have been evaluated by comparison with steady state temperature data from the THORS Facility at ORNL. Both codes give good predictions of transverse and axial temperatures when compared with wire wrap thermocouple data. The crossflow velocity profiles predicted by these codes are similar which is encouraging since the wire wrap models are based on different assumptions.

Research Organization:
Oak Ridge National Lab., TN (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
5904005
Report Number(s):
CONF-790816-22; TRN: 79-019253
Resource Relation:
Conference: International meeting on fast reactor safety technology, Seattle, WA, USA, 19 Aug 1979
Country of Publication:
United States
Language:
English