Chair: Tomio Okawa(UEC)

(1) Current status of experimental studies and measurement techniques in pool boiling

Shinichiro Uesawa (JAEA)

(2) Experimental investigation on transient critical heat flux in rod bundle

Takahiro Arai (CRIEPI)

(3) Challenges to validate two-phase flow and boiling simulation

Hiroyuki Yoshida(JAEA)

(4) Discussion about evaluation methods for critical heat flux

Ayako Ono (JAEA)

 

An evaluation method of critical heat flux based on a mechanism is needed to design the fuel assemblies in light water reactors efficiently and evaluate safety appropriately. The research committee for mechanistic evaluation of critical heat flux for nuclear reactors reviewed many studies and organized issues to be considered to establish the evaluation method of critical heat flux based on the mechanism. In this session, the activities and discussion results of the research committee will be reported.

 

Chair: Shinichi Morooka (Waseda Univ.)

(1) Overview of Research Activity for Offshore Floating Nuclear Power Plant

Daisuke Sasa (TEPCO)

(2) Feasibility Study of BWR for Offshore Floating Nuclear Power Plant

Chiaki Kino (IAE)

(3) BWR Plant Oscillation Analysis with Thermal Hydraulics-Neutronics Coupling

Masahiro Furuya (Waseda Univ.)

(4) Study on thermal-hydraulics related to OFNP in NEXIP and Perspectives toward Practical Elimination of Severe Accidents

Atsushi Ui (CRIEPI)

 

In Council on Competitiveness-Nippon (COCN), Offshore Floating Nuclear Power Plant (OFNP), which is a new concept of Nuclear Power Plant (NPP) to enhance safety based on the experience of the Fukushima Daiichi NPP accident has been discussed for two years. In this concept, a proven NPP on a cylindrical structure, which has been demonstrated on oil drilling rigs, floats several tens of kilometers offshore from the coast. From a point of view of industrial competitiveness, the concept will be highly feasible and promising.

In this session, a brief overview of OFNP discussed at COCN will be presented. Additionally, two-phase flow experiments conducted in NEXIP（Nuclear Energy × Innovation Promotion）, which is a Japanese national project sponsored by METI, passive safety systems using sea water and an influence of the oscillation on BWR core will be introduced. After the presentations, future prospects will be discussed with participants.