Whole Core Sub-Channel Analysis Verification with the EBR-II SHRT-17 Test

Conference · Sat Jul 01 00:00:00 EDT 2006

OSTI ID:21021148

Dunn, Floyd E; Cahalan, James E ^[1]; Dohee, Hahn; Hae-yong, Jeong ^[2]

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1. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (United States)
2. Korea Atomic Energy Research Institute, Yusong, P.O. Box 105, Daejon, 305-600 (Korea, Republic of)

As part of an International Nuclear Energy Research Initiative, Argonne National Laboratory and the Korea Atomic Energy Research Institute have cooperated in developing a detailed whole core coolant sub-channel model. This model has been implemented in LMR systems codes and coupled with the primary loop treatments in these codes. Analysis of the SHRT-17 test performed in the EBR-II reactor has been used for verification of the model. Detailed steady-state and transient coolant temperature profiles and subassembly flow rates are available for an instrumented subassembly that was in the core for this test. Calculated coolant temperatures and flow rates agree well with the measured values. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21021148
• Resource Relation: Conference: 2006 International congress on advances in nuclear power plants - ICAPP'06, Reno - Nevada (United States), 4-8 Jun 2006; Other Information: Country of input: France; 10 refs; Related Information: In: Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06, 2734 pages.
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COOLANTS
EBR-2 REACTOR
FLOW RATE
NUCLEAR ENERGY
STEADY-STATE CONDITIONS