LAPUR5.2 BWR Stability Analysis in Chinshan Nuclear Power Plant

Conference · Sat Jul 01 04:00:00 EDT 2006

OSTI ID:20997103

Hsieh, Chang-Lung; Shih, Chunkuan ^[1]; Lin, Hao-Tzu; Wang, Jong-Rong ^[2]; Chiang, Show-Chuyan; Weng, Tong-Li ^[3]

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1. Department of Engineering and System Science, National Tsing-Hua University, Hsinchu 300, Taiwan (China)
2. Institute of Nuclear Energy Research, AEC ROC, P.O. Box 3-3, 1000 Wenhua Road, Lung-Tan 325, Taiwan (China)
3. Department of Nuclear Safety, Taiwan Power Company, 242, Sec. 3, Roosevelt Road, Taipei, Taiwan (China)

Boiling water reactors have the unique coupling mechanisms between neutronic and two-phase flow thermal-hydraulic behaviors and may induce instability by unstable power/flow oscillations. At each core reload design, it is important to employ decay ratio for the purpose of analyzing system stability and determining its operating boundary. Making use of LAPUR5.2 and SIMULATE-3 codes, we have established a methodology to conduct such analysis. Comparisons made with vendor's STAIF results indicated good agreements in decay ratios for Chinshan Nuclear Power Plant Unit 2 Cycle 21 reload design. This research focuses on the parametric sensitivity effect on the variation of decay ratio for different power/flow operating points. Based on the result of sensitivity studies, we presented fractional changes of decay ratios by varying certain important parameters under different power/flow points. It is concluded that density reactivity coefficient, gap conductance and recirculation loop gain on high operating power/flow points have larger fractional change of decay ratio. (authors)

• Research Organization: The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
• OSTI ID: 20997103
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
COMPARATIVE EVALUATIONS
DENSITY
DESIGN
INSTABILITY
NUCLEAR POWER PLANTS
REACTIVITY COEFFICIENTS
SENSITIVITY
SENSITIVITY ANALYSIS
STABILITY
THERMAL HYDRAULICS
TWO-PHASE FLOW
VARIATIONS