Application of code scaling applicability and uncertainty methodology to the large break loss of coolant

Young, Michael Y.; Bajorek, Stephen M.; Nissley, M.E.; Hochreiter, L. E.

doi:10.1016/s0029-5493(98)00217-9

Cited by 46 publications

(21 citation statements)

References 5 publications

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“…The method was first demonstrated in 1996 for licensed application by Westinghouse to be structured, traceable, and practical [2]. Since then, Best Estimate Plus Uncertainty (BEPU) methods have been extensively used by the nuclear power industry around the world for power upratings, license renewals, and new design certifications.…”

Section: Overview Of Csau and Bepumentioning

confidence: 99%

Use of forward sensitivity analysis method to improve code scaling, applicability, and uncertainty (CSAU) methodology

Zhao

Mousseau

2012

Nuclear Engineering and Design

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Section: Overview Of Csau and Bepumentioning

confidence: 99%

Use of forward sensitivity analysis method to improve code scaling, applicability, and uncertainty (CSAU) methodology

Zhao

Mousseau

2012

Nuclear Engineering and Design

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“…Nonetheless, the CSAU process does provide a means to derive a robust solution to the large-break LOCA issue, specifically, and, possibly, to other large-scale engineering systems experiencing integral phenomenological influences. The AREVA realistic large-break LOCA (RLBLOCA) submission (AREVA, 2001) represents the third major demonstration of the CSAU methodology and the second time this methodology has been approved for the licensing of fuel reloads in the United States (Young et al, 1998).…”

Section: Introductionmentioning

confidence: 99%

AREVA's realistic large break LOCA analysis methodology

Martin

O'Dell

2005

Nuclear Engineering and Design

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“…It is based on the CSAU (Code Scaling, Applicability and Uncertainty) methodology, WCOBRA/TRAC computer code and use of response surfaces to estimate PCT uncertainty distribution with the 95th percentile PCT determined from a Monte Carlo sampling and accepted as the licensing basis PCT. At the beginning it was applicable to 3-and 4-loop plants with safety injection into the cold leg [56], [57]. Subsequently, the methodology applicability was extended to 2-loop plants with upper plenum injection in 1999 and advanced passive (AP) plant such as the AP600 and AP1000 [58] Its broader use in the future is therefore envisaged, even though it is not always feasible because of the difficulty of quantifying code uncertainties with sufficiently narrow range for every phenomenon and for each accident sequence.…”

mentioning

confidence: 99%

“…[ 87] . 56 uncertain input parameters (rank correlation coefficient) for the reference reactor large break [ 50], [ 97] Safety is an essential part for the peaceful use of nuclear power generation. The safety of nuclear power plants is based on the concept of defence in depth [1], Fig.…”

mentioning

confidence: 99%

Framework and Strategies for the Introduction of Best Estimate Models Into the Licensing Process

Sollima

Petrangeli

D'Auria

et al. 2009

Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition

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SOMMARIO. SBO and SBLOCA .................................. 48 4.2.4.1.3. Results of the analysis ......................................................... 49 4.2.4.1.4. Decay heat power ................................................................ 49 4.2.4.1.5. Hot rod temperature............................................................. 55 4.2.4.1.6. Analysis of the results .......................................................... 57 4.2.4.1.7. Conclusion ........................................................................... distribution..................... 59 4.2.4.2.3. Model and calculation cases................................................ 60 4.2.4.2.4. Evaluation of the cell probability .......................................... 61 4.2.4.2.5 LIST OF SYMBOLS U (1979) with 1973 ...................................................................................................... 70 Fig. 55 -LARGE reactor sin, 100 s, produced and absorbed power versus height fine model....................................................................................................... 70 Fig. 56 -CHF comparison, 7 MPa (RELAP5/Mod 2)............................................. 73 Fig. 57 -CHF Comparison 3 MPa (RELAP5/Mod2) .............................................. 73 Fig. 58 -LOFT: core cross flow model................................................................... 76 Fig. 59 -LOFT: core temperature .......................................................................... 76 Fig. 60 -LOFT: core mass flow ............................................................................. 77 Fig. 61 -PWR-1000: core cross flow model .......................................................... 78 Fig. 62 -PWR-1000: core temperature comparison.............................................. 79 Fig. 63 -PWR-1000 ...................................... 136 Fig. A.11 -Schematic processes in the Swedish reactor licensing program....... 137 Fig. A.12 -Schematic of steps in the Swedish reactor licensing program .......... 138 Fig. A.13 -VVER 1000, Steady State: Up and SGs (1 to 4) pressure ................ 143 Fig. A.14 -VVER 1000, Steady State: Core inlet mass flowrate......................... 144 Fig. A.15 -VVER 1000, Steady State: Core and SG exchanged power ............. 144 Fig. A.16 -VVER 1000 1 (up to 11000s)........ 160 Fig. A.44 -Pressure in the upper plenum in the transient 2 (up to 8000s).......... 160 Fig. A.45 -Pressure in the upper plenum in the transient 1 (up to 1200s).......... 161 Fig. A.46 -Pressure in the upper plenum in the transient 2 (up to 1200s).......... 161 Fig. A.47 -Model of the LOFT and PWR core..................................................... 163 XVIII LIST OF TABLES INTRODUCTIONSafety is an essential part for the peaceful use of nuclear power generation. The safety of nuclear power plants is based on the concept of defence in depth [1], Fig. 1, which indicates successive physical barriers (fuel matrix, cladding, primary system pressure boundary and ...

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Application of code scaling applicability and uncertainty methodology to the large break loss of coolant

Cited by 46 publications

References 5 publications

Use of forward sensitivity analysis method to improve code scaling, applicability, and uncertainty (CSAU) methodology

Use of forward sensitivity analysis method to improve code scaling, applicability, and uncertainty (CSAU) methodology

AREVA's realistic large break LOCA analysis methodology

Framework and Strategies for the Introduction of Best Estimate Models Into the Licensing Process

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