Core Disruptive Accident Analysis using ASTERIA-FBR

Japan Nuclear Energy Safety Organization, Toranomon Towers Office, 4-1-28 Toranomon, Minato-ku, Tokyo, Japan 105-0001

^* Corresponding Author, E-mail: ishizu-tomoko@jnes.go.jp

Abstract

JNES is developing a core disruptive accident analysis code, ASTERIA-FBR, which tightly couples the thermal-hydraulics and the neutronics to simulate the core behavior during core disruptive accidents of fast breeder reactors (FBRs). ASTERIA-FBR consists of the three-dimensional thermal-hydraulics calculation module: CONCORD, the fuel pin behavior calculation module: FEMAXI-FBR, and the space-time neutronics module: Dynamic-GMVP or PARTISN/RKIN. This paper describes a comparison between characteristics of GMVP and PARTISN and summarizes the challenging issues on applying Dynamic-GMVP to the calculation against unprotected loss-of-flow (ULOF) event which is a typical initiator of core disruptive accident of FBR. The statistical error included in the calculation results may affect the super-prompt criticality during ULOF event and thus the amount of released energy.