[KSCI] Korea Science Citation Index Service

http://dx.doi.org/10.5516/NET.2007.39.4.257

SAFETY OF THE SUPER LWR

Ishiwatari, Yuki (Department of Nuclear Engineering and Management, The University of Tokyo)
Oka, Yoshiaki (Nuclear Professional School, The University of Tokyo)
Koshizuka, Seiichi (Department of Quantum Engineering and System Science, The University of Tokyo)

Publication Information

Nuclear Engineering and Technology / v.39, no.4, 2007 , pp. 257-272 More about this Journal

Abstract

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.

Keywords

Generation IV Reactor; SCWR; Once-Through Coolant cycle; Supercritical-Pressure; Safety;

Citations & Related Records

Times Cited By Web Of Science : 9 (Related Records In Web of Science)

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