Abstract
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.
Highlights
Today, considering the sustainability of the nuclear technology in the energy mix policy of developing and developed countries, the international community, taking into account the operational experience of the nuclear reactors, starts the development of new advanced reactor designs
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 International Atomic Energy Agency (IAEA) International Collaborative Standard Problem that is being hosted at Oregon State University (OSU) and the experimental data will be collected at the OSU-multi-application small light water reactor (MASLWR) test facility
The MASLWR [1, 2, 8,9,10,11,12,13], Figure 1, is a small modular integral pressurized water reactor (PWR) relying on natural circulation during both steady-state and transient operations
Summary
Today, considering the sustainability of the nuclear technology in the energy mix policy of developing and developed countries, the international community, taking into account the operational experience of the nuclear reactors, starts the development of new advanced reactor designs. After the completion of the first test series, through a grant from the International Atomic Energy Agency (IAEA), the OSU-MASLWR test facility core was reconfigured to eliminate a recurring grounding problem and improve facility reliability [12] in anticipation of conducting an IAEA ICSP on “Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Primary System and Containment During Accidents” [14,15,16] This ICSP is being hosted at OSU and the experimental data will be collected at the OSU-MASLWR facility, to provide experimental data on single-/two-phase flow instability phenomena under natural circulation conditions and coupled containment/ reactor vessel behavior in integral type light water reactors. A summary of the best estimate thermal hydraulic system code analyses, already performed, to investigate 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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