Thermal Conductivities of Granular UO2 Compacts with/without Uranium Particles

Ishii, Takeshi; Yuda, Ryoichi; Hirai, Masahiro; Tsuboi, Yasushi; Ukai, Shigeharu

doi:10.3327/jnst.41.1204

Cited by 4 publications

(4 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Concerning the thermal conductivity of the vibro-packed fuels, a previously developed model 4) was applied. Concerning the mechanical properties, compression tests of granular UO 2 compacts were conducted.…”

Section: Discussionmentioning

confidence: 99%

“…For the thermal conductivity of the unsintered region in vibro-packed fuel, a previously developed model, 4) which was based on the Hall and Martin model, 5) was applied and the effect of necking between fuel granules was taken into account. The model contained two simplified geometrical arrangements.…”

Section: Models For Thermochemical Properties Of the Vibropacked Granmentioning

confidence: 99%

See 1 more Smart Citation

Development of a Performance Analysis Code for Vibro-Packed MOX Fuels

Ishii

Nemoto²,

Asaga

et al. 2008

J. Nucl. Sci. Technol.

Self Cite

View full text Add to dashboard Cite

The compression characteristics and effective elastic moduli of granular UO 2 compacts were measured to evaluate the mechanical properties of vibro-packed MOX fuels. These properties were incorporated into a pellet-type fuel performance analysis code CEDAR with evaluation models for the thermochemical behaviors of the vibro-packed MOX fuels to develop a vibro-packed MOX fuel performance analysis code CEDAR-VIPAC, ver.1.0. Calculations were made by the developed code on a vibro-packed MOX fuel pin irradiated at BN-600 in Russia. The calculated stress-strain state showed that the contact pressure on the inner cladding surface was small enough not to cause local deformations due to excess FCMI. Additionally, the code results showed that the compression characteristics of the vibro-packed fuels contributed considerably to the central void formation or growth. Because they agreed well with the behaviors obtained from the experimental data, it is concluded that the code provided a reasonable explanation of the thermochemical and mechanical behaviors of vibro-packed MOX fuels under irradiation.

show abstract

Section: Discussionmentioning

confidence: 99%

Section: Models For Thermochemical Properties Of the Vibropacked Granmentioning

confidence: 99%

Development of a Performance Analysis Code for Vibro-Packed MOX Fuels

Ishii

Nemoto²,

Asaga

et al. 2008

J. Nucl. Sci. Technol.

Self Cite

View full text Add to dashboard Cite

show abstract

“…ÓAtomic Energy Society of Japan uniquely optimized by Japan Nuclear Cycle Development Institute (present JAEA), Toshiba Corporation, and Nippon Nuclear Fuel Development Co., Ltd. 2) The products of the U particles were classified into 150-106 mm or 106-75 mm. The density of the U particles was 18.94 g/cm 3 (99.40%TD) by the measurement with the immersion method.…”

Section: Methodsmentioning

confidence: 99%

Vibro-Packing Experiment of Non-Spherical Uranium Dioxide Particles with Spherical Metallic Uranium Particles

Matsuyama

Ishii

Hirai³

et al. 2007

Journal of Nuclear Science and Technology

Self Cite

View full text Add to dashboard Cite

Japan Atomic Energy Agency has developed vibro-packed fuel as one of the candidates for commercial fast breeder reactor fuels. In this study, vibro-packing experiments were carried out to investigate particle movement during vibro-packing as well as particle distribution after the completion of vibro-packing. Non-spherical uranium dioxide particles and spherical metallic uranium particles were used to simulate mixed oxide particles and oxygen getter particles, respectively. These experiments revealed the following facts. It is important to prevent segregation by means of feeding each size of the fuel particles uniformly into a cladding tube in order to disperse oxygen getter particles uniformly. ''Simultaneous feeding'' with volumetric powder feeders is useful to realize the above.

show abstract

“…uniquely optimized by Japan Nuclear Cycle Development Institute (present JAEA), Toshiba Corporation, and Nippon Nuclear Fuel Development Co., Ltd. 2) The products of the U particles were classified into 150-106 mm or 106-75 mm. The density of the U particles was 18.94 g/cm 3 (99.40%TD) by the measurement with the immersion method.…”

Section: Articlementioning

confidence: 99%