Sensitivity analysis of the MASLWR helical coil steam generator using TRACE

Mascari, Fulvio; Vella, Giuseppe; Woods, Brian; Welter, Kent; Pottorf, Jason; Young, E.; Adorni, M.; D'Auria, Francesco Saverio

doi:10.1016/j.nucengdes.2010.05.002

Cited by 23 publications

(27 citation statements)

References 6 publications

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“…BETHSY 6.2TC test was a 15.24 cm (6 inch) cold leg break in the loop no. 1 without available high pressure and low pressure safety injection system [6]. This test is a counterpart test of LSTF SB-CL-21 [16].…”

Section: Bethsy 62tcmentioning

confidence: 99%

“…Although the TRACE computer code is the future of US NRC, its use in countries members of Code Applications and Maintenance Program (CAMP) it is still not dominant against the RELAP5 computer code. Nevertheless, TRACE is now more and more used [6][7][8], also by RELAP5 users, because of better RELAP5 to TRACE conversion capability using SNAP as reported on CAMP meetings [9][10][11]. However, not much information is available in the open literature on RELAP5 to TRACE conversion.…”

Section: Introductionmentioning

confidence: 99%

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Advanced Presentation of BETHSY 6.2TC Test Results Calculated by RELAP5 and TRACE

Prošek

Berar

2012

Science and Technology of Nuclear Installations

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Today most software applications come with a graphical user interface, including U.S. Nuclear Regulatory Commission TRAC/RELAP Advanced Computational Engine (TRACE) best-estimate reactor system code. The graphical user interface is called Symbolic Nuclear Analysis Package (SNAP). The purpose of the present study was to assess the TRACE computer code and to assess the SNAP capabilities for input deck preparation and advanced presentation of the results. BETHSY 6.2 TC test was selected, which is 15.24 cm equivalent diameter horizontal cold leg break. For calculations the TRACE V5.0 Patch 1 and RELAP5/MOD3.3 Patch 4 were used. The RELAP5 legacy input deck was converted to TRACE input deck using SNAP. The RELAP5 and TRACE comparison to experimental data showed that TRACE results are as good as or better than the RELAP5 calculated results. The developed animation masks were of great help in comparison of results and investigating the calculated physical phenomena and processes.

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Section: Bethsy 62tcmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Advanced Presentation of BETHSY 6.2TC Test Results Calculated by RELAP5 and TRACE

Prošek

Berar

2012

Science and Technology of Nuclear Installations

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“…The MASLWR integral reactor concept [1,2,[8][9][10][11][12][13], developed by Idaho National Engineering and Environmental Laboratory, OSU, and NEXANT-Bechtel, Figure 1, is a small modular PWR relying on natural circulation during both steady-state and transient operation, which includes an integrated steam generator (SG) consisting of banks of vertical helical tubes contained within the reactor pressure vessel (RPV). The primary coolant flows outside the SG tubes and the feed-water (FW) is fully vaporized resulting in superheated steam at the SG exit.…”

Section: Introductionmentioning

confidence: 99%

“…OSU has constructed, under a US Department of Energy grant, a system-level test facility, OSU-MASLWR [1,2,[8][9][10][11][12][13], to examine natural circulation phenomena of importance to the MASLWR design. Four tests have been conducted in support of the MASLWR concept design verification.…”

Section: Introductionmentioning

confidence: 99%

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Analyses of the OSU-MASLWR Experimental Test Facility

Mascari

Vella

Woods

et al. 2012

Science and Technology of Nuclear Installations

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Today, considering the sustainability of the nuclear technology in the energy mix policy of developing and developed countries, the international community starts the development of new advanced reactor designs. In this framework, Oregon State University (OSU) has constructed, a system level test facility to examine natural circulation phenomena of importance to multi-application small light water reactor (MASLWR) design, a small modular pressurized water reactor (PWR), relying on natural circulation during both steady-state and transient operation. The target of this paper is to give a review of the main characteristics of the experimental facility, to analyse the main phenomena characterizing the tests already performed, the potential transients that could be investigated in the facility, and to describe the current IAEA International Collaborative Standard Problem that is being hosted at OSU and the experimental data will be collected at the OSU-MASLWR test facility. A summary of the best estimate thermal hydraulic system code analyses, already performed, to analyze the codes capability in predicting the phenomena typical of the MASLWR prototype, thermal hydraulically characterized in the OSU-MASLWR facility, is presented as well.

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