Comparative methodology between actual RCCS and downscaled heat-removal test facility

Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita

研究成果: ジャーナルへの寄稿記事

抄録

Previously, a reactor cavity cooling system (RCCS) has been reported with passive safety features comprising of two continuous closed regions, namely an ex-reactor pressure vessel region and cooling region with a heat-transfer surface to ambient air. The novel shape of the RCCS allows it to efficiently remove heat released from the reactor pressure vessel (RPV) via thermal radiation and natural convection. The RCCS design significantly reduces the possibility of losing the heat sink for decay heat-removal during nuclear accidents including a station blackout by employing air as a working fluid and ambient air as ultimate heat sink. RCCS has the potential to stably and passively remove heat released from the RPV and decay heat following a reactor shutdown. The RCCS achieved a heat-removal rate of approximately 3 kW/m2. On the contrary, the heat fluxes from the RPV surface of the high temperature engineering test reactor and commercial high temperature gas-cooled reactors are 1.23–2.46 kW/m2 and approximately 3.0 kW/m2, respectively. In the previous report, the authors changed the adiabatic boundary conditions and considered the heat dissipation effect from the RPV region to ground through the RCCS wall via heat conduction; therefore, the authors could improve the system's heat-removal capability to increase its thermal reactor power level. Moreover, considering the possibilities for doubling the heat-transfer areas and increasing the emissivities, heat flux removed by the RCCS could potentially reach 7.0 kW/m2. Herein, the authors conduct a comparative methodology between an actual RCCS and a downscaled heat-removal test facility.

元の言語英語
ページ(範囲)830-836
ページ数7
ジャーナルAnnals of Nuclear Energy
133
DOI
出版物ステータス出版済み - 11 1 2019

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Test facilities
Cooling systems
Pressure vessels
Heat sinks
Heat flux
High temperature engineering
Air
Reactor shutdowns
Heat transfer
High temperature gas reactors
Hot Temperature
Heat radiation
Heat losses
Natural convection
Heat conduction
Accidents
Systems analysis
Boundary conditions
Cooling
Fluids

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

これを引用

Comparative methodology between actual RCCS and downscaled heat-removal test facility. / Takamatsu, Kuniyoshi; Matsumoto, Tatsuya; Liu, Wei; Morita, Koji.

:: Annals of Nuclear Energy, 巻 133, 01.11.2019, p. 830-836.

研究成果: ジャーナルへの寄稿記事

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