2017 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2F06-08] Analysis Method Development and V&V 1

Tue. Mar 28, 2017 11:10 AM - 12:00 PM Room F (16-206 Building No.16)

Chair: Takanori Kitada (Osaka Univ.)

11:10 AM - 11:25 AM

[2F06] Development of Core Nuclear Analysis Method using Direct Response Matrix

(13)Correction Method of Instantaneous Subchannel Void Distribution

*Takeshi Mitsuyasu1,2, Motoo Aoyama1, Akio Yamamoto2 (1. Hitachi, Ltd., 2. Nagoya University)

Keywords:BWR, Subchannel, Void, Response matrix

The correction method of instantaneous subchannel void distribution which changes due to pin-by-pin power distribution has been developed toward boiling water reactor cores. The method was adopted to direct response matrix method which could evaluate pin-by-pin power distribution, and validated using a system of a few assemblies.