Refinement of Transient Criteria and Safety Analysis for a High-Temperature Reactor Cooled by Supercritical Water

Abstract In past designs of supercritical water-cooled reactors, the core flow rate has had to be kept high enough to satisfy the minimum deterioration heat flux ratio criterion where the deterioration heat flux is a function of the core flow rate. Refinement of transient criteria related to the fuel rod design is undertaken, and new dominant transient criteria are proposed in which the cladding temperature is <610°C for Type 316 stainless steel and <840°C for Inconel 700 to reduce the balance of the plant and improve the thermal efficiency. The safety analysis for the high-temperature core using these new criteria is carried out. All the analyzed events satisfy the new criteria. A new formula for the heat transfer correlation at supercritical pressure is proposed based on numerical simulation.

[1]  Yoshiaki Oka,et al.  Core design of a high-temperature fast reactor cooled by supercritical light water , 1999 .

[2]  Yoshiaki Oka,et al.  Pressure- and Flow-Induced Accident and Transient Analyses of a Direct-Cycle, Supercritical-Pressure, Light-Water-Cooled Fast Reactor , 1998 .

[3]  Yoshiaki Oka,et al.  Conceptual design of a high temperature power reactor cooled and moderated by supercritical light water , 1998 .

[4]  Yoshiaki Oka,et al.  Negative coolant void reactivity in large fast breeder reactors with hydrogenous moderator layer , 1996 .

[5]  Yasushi Okano,et al.  Core Design of a Direct-Cycle, Supercritical-Pressure, Light Water Reactor with Double Tube Water Rods , 1996 .

[6]  S. Koshizuka,et al.  Numerical analysis of deterioration phenomena in heat transfer to supercritical water , 1995 .

[7]  T. Fujii,et al.  Forced convective heat transfer to supercritical water flowing in tubes , 1972 .

[8]  W. Jones,et al.  The prediction of laminarization with a two-equation model of turbulence , 1972 .

[9]  Yoshiaki Oka,et al.  Conceptual design study of advanced power reactors , 1998 .

[10]  李鐘鎬.  LOCA Analysis and Safety System Consideration for the Supereritical-Water Cooled Reactor(超臨界圧軽水冷却炉の冷却材喪失事故解析と安全系の考察) , 1996 .

[11]  Yoshiaki Oka,et al.  Systems design of direct-cycle supercritical-water-cooled fast reactors , 1995 .

[12]  S. Koshizuka,et al.  Supercritical-pressure, light-water-cooled reactors for improving economy, safety, plutonium utilization and environment , 1995 .