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Journal Articles

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 B$$_{4}$$C

Liu, X.*; Morita, Koji*; Yamano, Hidemasa

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.47 - 51, 2019/09

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 B$$_{4}$$C 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 B$$_{4}$$C 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 B$$_{4}$$C pellet and SS to investigate the temperature sensitivity on the eutectic reaction behavior.

JAEA Reports

PNC Technical Review No.103

PNC TN1340 97-003, 101 Pages, 1997/09

PNC-TN1340-97-003.pdf:12.06MB

no abstracts in English

JAEA Reports

PNC Technical Review No.101

PNC TN1340 97-001, 154 Pages, 1997/03

PNC-TN1340-97-001.pdf:21.55MB

no abstracts in English

Oral presentation

Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 10; Development of eutectic reaction model for use in reactor safety analysis code

Liu, X.*; Morita, Koji*; Yamano, Hidemasa

no journal, , 

A physical model used in a fast reactor safety analysis code, SIMMER-III, was developed in order to simulate a eutectic melting reaction and relocation behavior of boron carbide (B$$_{4}$$C) as a control rod material and stainless steel (SS) in core disruptive accidents of sodium-cooled fast reactors. In addition, basic applicability was confirmed with estimation for existing visualization experiments of eutectic melts.

Oral presentation

Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 18; Validation of eutectic reaction model for use in reactor safety analysis code

Liu, X.*; Morita, Koji*; Yamano, Hidemasa

no journal, , 

The purpose of this project is to simulate the eutectic reaction between control rod material, B$$_{4}$$C, and stainless steel, and the relocation behavior of the eutectic compound during a core disruptive accident in a sodium-cooled fast reactor. The authors are developing their physical models for a safety analysis code. In this study, the authors have conducted numerical analyses of the basic experiments for liquifaction of control rod, and examined the applicability of the physical model.

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