Assessment of BETHSY Test 9.1.b using RELAP5/MOD3. International Agreement Report
- Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
The 2`` cold leg break test 9.l.b, conducted at the BETHSY facility was analyzed using the RELAP5/MOD3 Version 5m5 code. The test 9.l.b was conducted with the main objective being the investigation of the thermal-hydraulic mechanisms responsible for the large core uncovery and fuel heat-up, requiring the implementation of an ultimate procedure. The present analysis demonstrates the code`s capability to predict, with sufficient accuracy, the main phenomena occurring in the depressurization transient, both from a qualitative and quantitative point of view. Nevertheless, several differences regarding the evolution of phenomena and affecting the timing order have to be pointed out in the base calculation. Three calculations were carried out to study the sensitivity to change of the nodalization in the components of the loop seal cross-over legs, and of the auxiliary feedwater control logics, and of the break discharge coefficient.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 10176678
- Report Number(s):
- NUREG/IA-0103; ON: TI93017983
- Resource Relation:
- Other Information: DN: Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP); PBD: Jun 1993
- Country of Publication:
- United States
- Language:
- English
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LOSS OF COOLANT
HEAT TRANSFER
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REACTOR SAFETY
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INTERNATIONAL AGREEMENTS
EVALUATION
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220900
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MATHEMATICS AND COMPUTERS