SAMPLING BASED UNCERTAINTY ANALYSIS OF 10 % HOTLEG BREAK LOCA IN LARGE SCALE TEST FACILITY

SAMIRAN SENGUPTA; S. K. DUBEY; R. S. RAO; S. K. GUPTA; V. K RAINA

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자료유형: 학술저널

저자정보: SAMIRAN SENGUPTA S. K. DUBEY R. S. RAO S. K. GUPTA V. K RAINA

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제42권 제6호

발행연도: 2010.1

수록면: 690 - 703 (14page)

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Sampling based uncertainty analysis was carried out to quantify uncertainty in predictions of best estimate codeRELAP5/MOD3.2 for a thermal hydraulic test (10% hot leg break LOCA) performed in the Large Scale Test Facility (LSTF)as a part of an IAEA coordinated research project. The nodalisation of the test facility was qualified for both steady state andtransient level by systematically applying the procedures led by uncertainty methodology based on accuracy extrapolation(UMAE); uncertainty analysis was carried out using the Latin hypercube sampling (LHS) method to evaluate uncertainty forten input parameters. Sixteen output parameters were selected for uncertainty evaluation and uncertainty band between 5thand 95thpercentile of the output parameters were evaluated. It was observed that the uncertainty band for the primary pressure duringtwo phase blowdown is larger than that of the remaining period. Similarly, a larger uncertainty band is observed relating toaccumulator injection flow during reflood phase. Importance analysis was also carried out and standard rank regression coefficientswere computed to quantify the effect of each individual input parameter on output parameters. It was observed that the breakdischarge coefficient is the most important uncertain parameter relating to the prediction of all the primary side parametersand that the steam generator (SG) relief pressure setting is the most important parameter in predicting the SG secondary pressure.

#Accident Analysis #Latin Hypercube Sampling #LOCA #LSTF #UMAE #Uncertainty

참고문헌 (11)

참고문헌 신청

A. Petruzzi / 2005 / Description of the Procedure to Qualify the Nodalisation and to Analyze the Code Results

D. M. Hamby / 1994 / A Review of Sensitivity Analysis Techniques (U)

K. Tasaka / 1985 / ROSA-IV Large Scale Test Facility System Description

K. Tasaka / 1989 / Supplemental Description of ROSAIV/ LSTF with no.1 Simulated Fuel-ROD Assembly

M. Khatib-Rahbar / 1989 / A probabilistic approach to quantifying uncertainties in the progression of severe accidents / Nuclear Science & Engineering 102 : 219 ~ 259

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