Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors: (5) Validation of a multi-phase model for eutectic reaction between molten stainless steel and B4C

Xiaoxing Liu, Koji Morita, Hidemasa Yamano

研究成果: Contribution to conferencePaper査読

抄録

Investigation of the eutectic reaction in a core disruptive accident of sodium cooled reactor is of importance since reactor criticality will be affected by the change in reactivity after eutectic reaction. In this study, we performed 1st step of validation analysis using a fast reactor safety analysis code, SIMMER-III, with the developed model based on a new series of experiments, where a B4C pellet was immersed into a molten stainless steel (SS) pool. The simulation results showed the general behavior of eutectic material formation measured in the experiments reasonably. The eutectic reaction consumes solid B4C and liquid SS, and then the liquid eutectic composition is produced at the early stage of reaction due to the high temperature of molten SS. Movement of the eutectic material in the molten pool leads to the redistribution of boron element. Molten SS pool then freezes to solid SS and movement of eutectic material is stopped by surrounding solid SS. Boron concentration in the pool was measured after molten SS freezes into a solid. Simulation results indicate that boron tends to accumulate in the upper part of the molten pool. This is attributed to the buoyancy force acting on lighter boron in the molten SS pool. A parametric study was also conducted by changing the initial temperature of B4C pellet and SS to investigate the temperature sensitivity on the eutectic reaction behavior.

本文言語英語
ページ47-51
ページ数5
出版ステータス出版済み - 1 1 2020
イベント14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, 米国
継続期間: 9 22 20199 27 2019

会議

会議14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
Country米国
CitySeattle
Period9/22/199/27/19

All Science Journal Classification (ASJC) codes

  • Fuel Technology
  • Nuclear Energy and Engineering

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