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Journal Articles

Development of fuel performance analysis code, BISON for MOX, named Okami; Analyses of pore migration behavior to affect the MA-bearing MOX fuel restructuring

Ozawa, Takayuki; Hirooka, Shun; Kato, Masato; Novascone, S.*; Medvedev, P.*

Journal of Nuclear Materials, 553, p.153038_1 - 153038_16, 2021/09

 Times Cited Count:4 Percentile:56.94(Materials Science, Multidisciplinary)

To evaluate the O/M dependence of pore migration regarding fuel restructuring at the beginning of irradiation, we are developing BISON for MOX in cooperation with INL and have installed pore migration model considering vapor pressure of vapor species and thermal conductivity for MOX. The O/M dependence of fuel restructuring observed in MA-bearing MOX irradiation experiment in Joyo was evaluated by the 2-dimensional analyses. Four MA-bearing MOX pins with different O/M ratio and pellet/cladding gap size were irradiated in Joyo B14 experiment. Remarkable restructuring of stoichiometric MA-bearing MOX fuels was observed in PIE, and could be evaluated by considering the influence of O/M ratio on vapor pressure. Also, a central void assumes to move toward wide-gap side when the pellet eccentricity taking place, but 2-dimentional analyses on pellet transverse section revealed that the central void formation observed in PIE would be inconsistent with a direction of the pellet eccentricity.

Oral presentation

Evaluation of pore migration behavior during irradiation to affect the MA-bearing MOX fuel restructuring by 2-dimensional analyses

Ozawa, Takayuki; Hirooka, Shun; Kato, Masato; Verdolin, F.*; Novascone, S.*

no journal, , 

3-dimensional analysis code BISON-MOX to be applied for the irradiation behavior of MOX fuels is being developed by installing MOX fuel properties and analysis models to BISON, which has been developed in INL. Applying the thermal conductivity of MOX fuel and the pore migration model based on vapor pressure of vapor species, the O/M dependence of fuel restructuring observed in MA-bearing MOX fuels irradiation in Joyo were evaluated by 2-dimensional analyses with BISON-MOX.

Oral presentation

Two dimensional analyses for pore migration behaviour to affect the MA-bearing MOX fuel restructuring

Ozawa, Takayuki; Hirooka, Shun; Kato, Masato; Novascone, S.*; Medvedev, P.*

no journal, , 

To evaluate the O/M dependence of pore migration regarding fuel restructuring at the beginning of irradiation, we are developing BISON for MOX in cooperation with INL and have installed pore migration model considering vapor pressure of vapor species and thermal conductivity for MOX. The O/M dependence of fuel restructuring observed in MA-bearing MOX irradiation experiment in Joyo was evaluated by the 2-dimensional analyses. Four MA-bearing MOX pins with different O/M ratio and pellet/cladding gap size were irradiated in Joyo B14 experiment. Remarkable restructuring of stoichiometric MA-bearing MOX fuels was observed in PIE, and could be evaluated by considering the influence of O/M ratio on vapor pressure. Also, a central void assumes to move toward wide-gap side when the pellet eccentricity taking place, but 2-dimentional analyses on pellet transverse section revealed that the central void formation observed in PIE would be inconsistent with a direction of the pellet eccentricity.

Oral presentation

Application of numerical simulation technology to the development of nuclear fuels, 2; Development of irradiation behavior simulation for fast reactor MOX fuels

Ozawa, Takayuki; Ikusawa, Yoshihisa; Hirooka, Shun; Kato, Masato; Novascone, S.*; Medvedev, P.*

no journal, , 

As MOX fuels are irradiation under higher linear power conditions up to high burnup in fast reactor, their irradiation behaviors are influenced by properties at high temperature over 2,000 K, FP accumulation and fast neutron irradiation. However, it is difficult to measure and evaluate fuel properties at high temperature, and it takes much cost and long time to evaluate MOX fuel behavior with the actual irradiation tests. In JAEA, based on knowledge accumulated from study on fuel properties and existing results of irradiation tests, a multi-dimension performance code for fast reactor MOX fuels has been developed in cooperation with Idaho National Laboratory (INL) in the framework of the Civil Nuclear Energy Working Group (CNWG) between Japan and the US. The current status and the future subjects of development of irradiation behavior simulation for fast reactor MOX fuels will be introduced.

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