Application of the W̱COBRA/TRAC best-estimate methodology to the AP600 large-break LOCA analysis

Zhang, Jinzhao; Bajorek, Stephen M.; Kemper, R.M.; Nissley, M.E.; Petkov, Nikolay; Hochreiter, L.E.

doi:10.1016/s0029-5493(98)00279-9

Cited by 19 publications

(4 citation statements)

References 2 publications

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“…Thus, a comparison with a best-estimate TRACE simulation shows great differences and this is not the issue of this paper. On the other hand, AP1000 LBLOCA sequence evolution presents a quite similar behavior to that predicted previously for AP600, see Zhang et al (1998) and Kemper and Vertes (1989).…”

Section: Ap1000 Lbloca Reference Casesupporting

confidence: 83%

“…When a phenomenon is identified as significative, it is ranked with high, medium or low importance depending upon the case, (Corletti, 2001). The dominant phenomena identified by Westinghouse for (Westinghouse, 2001 andZhang et al, 1998) Hence, it is reasonably to select, for uncertainty evaluations, the parameters related with such phenomena and/or processes, (Leslie, 2008;Westinghouse, 2001 andChao, 2011). The uncertainty parameters selected for this study along with its relationship with important phenomena is listed in Table 6.…”

Section: Bepu Methodologies Non Parametric Methodsmentioning

confidence: 99%

See 1 more Smart Citation

AP1000® Large-Break LOCA BEPU analysis with TRACE code

Queral

Montero-Mayorga

Gonzalez-Cadelo

2015

Annals of Nuclear Energy

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Section: Ap1000 Lbloca Reference Casesupporting

confidence: 83%

Section: Bepu Methodologies Non Parametric Methodsmentioning

confidence: 99%

AP1000® Large-Break LOCA BEPU analysis with TRACE code

Queral

Montero-Mayorga

Gonzalez-Cadelo

2015

Annals of Nuclear Energy

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“…A literature survey reveals that there have been many experimental and numerical investigations on the characteristics of different PRHRSs. The Westinghouse advanced passive PWRs, AP-600, AP-1000, and EP-1000 (IAEA-TECDOC-1391, 2004; Adomaitis et al [1]; Reyes and Hochreiter [2]; Zhang et al [3]) adopt passive core cooling system (PXS) to protect the plant against reactor coolant system (RCS) leaks and ruptures of various sizes and locations. The PXS includes a 100% capacity passive residual heat removal heat exchanger (PRHR HX), which satisfies the safety criteria for loss of feedwater, feedwater and steam line breaks.…”

Section: Introductionmentioning

confidence: 99%

Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor

Gou

Qiu

et al. 2009

Science and Technology of Nuclear Installations

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A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS), which is connected to the reactor coolant system via the secondary side of the steam generator, for an integral pressurized water reactor is presented in this paper. Three-interknited natural circulation loops are adopted by this PRHRS to remove the residual heat of the reactor core after a reactor trip. Based on the one-dimensional model and a simulation code (SCPRHRS), the transient behaviors of the PRHRS as well as the effects of the height difference between the steam generator and the heat exchanger and the heat transfer area of the heat exchanger are studied in detail. Through the calculation analysis, it is found that the calculated parameter variation trends are reasonable. The higher height difference between the steam generator and the residual heat exchanger and the larger heat transfer area of the residual heat exchanger are favorable to the passive residual heat removal system.

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“…Часто такие вопросы возникают в связи с проблемами безопасности. Типичный и очевидный (по применимости к нему дан-ных вопросов) пример, который и рассматривается в работе, -атомная энергетика [1][2][3][4][5][6][7][8].…”

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