2019 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 305-1 Computational Science and Engineering

[2K06-10] Reactor and Safety Analysis

Thu. Mar 21, 2019 2:45 PM - 4:10 PM Room K (Common Education Bildg. 2 3F No.33)

Chair:Satoshi Wada(TOSHIBA ESS)

3:30 PM - 3:45 PM

[2K09] Development of Severe Accident Analysis Code SAMPSON

(3) Improvement of Control Interface Module

*Naotoshi Tominaga1,2, Richard Finger1,3, Masao Chaki1 (1. The Institute of Applied Energy, 2. currently Advancesoft, 3. currently Goldman Sachs Japan)

Keywords:SAMPSON, severe accident code, simulation

Since 1993, SAMPSON has been developed as domestic produced code which can perform accident analysis from reactor vessel event to reactor containment event. After the accident at Fukushima Daiichi Nuclear Plant, Institute of Applied Energy improved the model in SAMPSON code and performed the accident analysis which is based on the accident progress and currently continues developing the code. This is continued presentation and we will present control interface for coupled analysis methodology and analysis for validation.