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YUKI ISHIWATARI 한국원자력학회 2007 Nuclear Engineering and Technology Vol.39 No.4
Supercritical water-cooled reactors (SCWRs) are recognized as a Generation IV reactor concept. The Super LWR is a pressure-vessel type thermal spectrum SCWR with downward-flow water rods and is currently under study at the University of Tokyo. This paper reviews Super LWR safety. The fundamental requirement for the Super LWR, which has a oncethrough coolant cycle, is the core coolant flow rate rather than the coolant inventory. Key safety characteristics of the Super LWR inhere in the design features and have been identified through a series of safety analyses. Although loss-of-flow is the most important abnormality, fuel rod heat-up is mitigated by the “heat sink” and “water source” effects of the water rods. Response of the reactor power against pressurization events is mild due to a small change in the average coolant density and flow stagnation of the once-through coolant cycle. These mild responses against transients and also reactivity feedbacks provide good inherent safety against anticipated-transient-without-scram (ATWS) events without alternative actions. Initiation of an automatic depressurization system provides effective heat removal from the fuel rods. An “in-vessel accumulator” effect of the reactor vessel top dome enhances the fuel rod cooling. This effect enlarges the safety margin for large LOCA.
Ishiwatari, Yuki,Oka, Yoshiaki,Koshizuka, Seiichi Korean Nuclear Society 2007 Nuclear Engineering and Technology Vol.39 No.4
Supercritical water-cooled reactors (SCWRs) are recognized as a Generation IV reactor concept. The Super LWR is a pressure-vessel type thermal spectrum SCWR with downward-flow water rods and is currently under study at the University of Tokyo. This paper reviews Super LWR safety. The fundamental requirement for the Super LWR, which has a once-through coolant cycle, is the core coolant flow rate rather than the coolant inventory. Key safety characteristics of the Super LWR inhere in the design features and have been identified through a series of safety analyses. Although loss-of-flow is the most important abnormality, fuel rod heat-up is mitigated by the "heat sink" and "water source" effects of the water rods. Response of the reactor power against pressurization events is mild due to a small change in the average coolant density and flow stagnation of the once-through coolant cycle. These mild responses against transients and also reactivity feedbacks provide good inherent safety against anticipated-transient-without-scram (ATWS) events without alternative actions. Initiation of an automatic depressurization system provides effective heat removal from the fuel rods. An "in-vessel accumulator" effect of the reactor vessel top dome enhances the fuel rod cooling. This effect enlarges the safety margin for large LOCA.
Three-dimensional Core Design of a Super Fast Reactor with a High Power Density
LIANGZHI CAO,YOSHIAKI OKA,YUKI ISHIWATARI,SATOSHI IKEJIRI,HAITAO JU 한국원자력학회 2010 Nuclear Engineering and Technology Vol.42 No.1
The SuperCritical Water-cooled Reactor (SCWR) pursues high power density to reduce its capital cost. The fast spectrum SCWR, called a super fast reactor, can be designed with a higher power density than thermal spectrum SCWR. The mechanism of increasing the average power density of the super fast reactor is studied theoretically and numerically. Some key parameters affecting the average power density, including fuel pin outer diameter, fuel pitch, power peaking factor, and the fraction of seed assemblies, are analyzed and optimized to achieve a more compact core. Based on those sensitivity analyses, a compact super fast reactor is successfully designed with an average power density of 294.8 W/cm3. The core characteristics are analyzed by using three-dimensional neutronics/thermal-hydraulics coupling method. Numerical results show that all of the design criteria and goals are satisfied.
THREE-DIMENSIONAL CORE DESIGN OF A SUPER FAST REACTOR WITH A HIGH POWER DENSITY
Cao, Liangzhi,Oka, Yoshiaki,Ishiwatari, Yuki,Ikejiri, Satoshi,Ju, Haitao Korean Nuclear Society 2010 Nuclear Engineering and Technology Vol.42 No.1
The SuperCritical Water-cooled Reactor (SCWR) pursues high power density to reduce its capital cost. The fast spectrum SCWR, called a super fast reactor, can be designed with a higher power density than thermal spectrum SCWR. The mechanism of increasing the average power density of the super fast reactor is studied theoretically and numerically. Some key parameters affecting the average power density, including fuel pin outer diameter, fuel pitch, power peaking factor, and the fraction of seed assemblies, are analyzed and optimized to achieve a more compact core. Based on those sensitivity analyses, a compact super fast reactor is successfully designed with an average power density of 294.8 W/$cm^3$. The core characteristics are analyzed by using three-dimensional neutronics/thermal-hydraulics coupling method. Numerical results show that all of the design criteria and goals are satisfied.
The Aqua-Planet Experiment (APE): Response to Changed Meridional SST Profile
WILLIAMSON, David L.,BLACKBURN, Michael,NAKAJIMA, Kensuke,OHFUCHI, Wataru,TAKAHASHI, Yoshiyuki O.,HAYASHI, Yoshi-Yuki,NAKAMURA, Hisashi,ISHIWATARI, Masaki,McGREGOR, John L.,BORTH, Hartmut,WIRTH, Volkm Meteorological Society of Japan 2013 Journal of the Meteorological Society of Japan Vol.a91 No.-
The Aqua-Planet Experiment (APE): CONTROL SST Simulation
BLACKBURN, Michael,WILLIAMSON, David L.,NAKAJIMA, Kensuke,OHFUCHI, Wataru,TAKAHASHI, Yoshiyuki O.,HAYASHI, Yoshi-Yuki,NAKAMURA, Hisashi,ISHIWATARI, Masaki,McGREGOR, John L.,BORTH, Hartmut,WIRTH, Volkm Meteorological Society of Japan 2013 Journal of the Meteorological Society of Japan Vol.a91 No.-