Testing of the multi-application small light water reactor (MASLWR) passive safety systems

Reyes, J.N.; Groome, John; Woods, Brian; Young, E.; Abel, K.; Yao, You; Yoo, Yeon Jong

doi:10.1016/j.nucengdes.2007.01.014

Cited by 45 publications

(35 citation statements)

References 3 publications

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“…The RTF is an integral test facility designed to evaluate the characteristics of natural circulation under steady-state and transient conditions and simulate the thermal-hydraulic system behavior during hypothetical accidents [13]. Since the previous IET facilities, such as VISTA [31] and OSU-MASLWR [32], are equipped with active systems under normal operation condition, a new testing program is required to obtain the experimental data on the safety performance of an integral PWR operating in a passive manner as REX-10. Figure 17 shows the experimental apparatus of the RTF.…”

Section: Validation With Ietmentioning

confidence: 99%

Assessment of TAPINS code for application to thermal-hydraulic analysis of an integral reactor, REX-10

Lee

Park

2013

Journal of Nuclear Science and Technology

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The thermal-hydraulic analysis program for integral reactor system (TAPINS) is a thermal-hydraulic system code developed by Seoul National University for transient analysis of an integral reactor, REX-10. Specialized for a fully passive integral pressurized water reactor, TAPINS adopts a one-dimensional fourequation drift-flux model for two-phase flows. It also consists of component models for the core, the helicalcoil steam generator, and the steam-gas pressurizer. This paper presents the developmental assessment of TAPINS to validate its applicability to the thermal-hydraulic analysis of REX-10. Assessment problems are determined by taking into account thermal-hydraulic phenomena expected during design basis accidents of REX-10, including the loss-of-feedwater accident and the small-break loss-of-coolant accident. To confirm the predictive capability of TAPINS for these phenomena, the TAPINS model is validated against four sets of separate effects problems, including the pressurizer insurge test, the subcooled boiling experiment, the critical flow test, and the Edwards pipe problem. In addition, the calculation results of TAPINS are compared with the experimental data obtained from a series of integral effects tests using a scaled apparatus of REX-10. From the validation results, it is demonstrated that TAPINS can provide the reasonable prediction on the thermal-hydraulic responses of REX-10 during the transient and accident conditions.

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Section: Validation With Ietmentioning

confidence: 99%

Assessment of TAPINS code for application to thermal-hydraulic analysis of an integral reactor, REX-10

Lee

Park

2013

Journal of Nuclear Science and Technology

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“…The MASLWR (Modro et al, 2003;Reyes et al 2007, Mascari et al, 2011aMascari et al, 2011e), figure 1, is a small modular integral PWR of 35 MWe developed by Idaho National Engineering and Environmental Laboratory, OSU and Nexant-Bechtel. During steady state condition the primary fluid, in single phase natural circulation, removes the core power and transfers it to the secondary fluid through helical coil SG.…”

Section: Maslwr Conceptual Design and Sbloca Mitigation Strategymentioning

confidence: 99%

“…Since the experimental data produced have to be applicable to the full-scale prototype, the geometrical characteristics of the facility and the initial and boundary conditions of the selected tests have to be correctly scaled. Since possible scaling distortions are present in the experimental facility design, the similitude of the main thermal hydraulic phenomena of interest has to be assured permitting their accurate experimental simulation (Zuber, 1991;Reyes, 2005b;Reyes et al, 2007;Mascari et al, 2011e). Fig.…”

Section: Introductionmentioning

confidence: 99%

“…1. MASLWR conceptual design layout (Modro et al, 2003;Reyes et al, 2007;Mascari et al, 2011a). Different computer codes have been developed to characterize two-phase flow systems, from a system and a local point of view.…”

Section: Introductionmentioning

confidence: 99%

“…The scaling analysis of the OSU-MASLWR experimental facility was performed in order to have an adequately simulation of the single and two-phase natural circulation, reactor system depressurization during a blowdown and the containment pressure response typical of the MASLWR prototype (Zuber, 1991;Reyes & King, 2003;Reyes, 2005b). A previous testing program has been conducted in order to assess the operation of the prototypical MASLWR under normal full pressure and full temperature conditions and to assess the passive safety systems under transient conditions (Modro et al 2003;Reyes & King, 2003;Reyes, 2005b;Reyes et al, 2007;Mascari et al, 2011e). The experimental data developed are useful also for the assessment and validation of the computational tools necessary for the operation, design and safety analysis of nuclear reactors.…”

Section: Introductionmentioning

confidence: 99%

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