Physicochemical interaction of oxide fuel with the cladding of the fuel elements of A fast reactor

V. A. Tsykanov; E. F. Davydov; E. P. Klochkov; V. K. Shamardin; V. N. Golovanov; F. N. Kryukov

doi:10.1007/bf01124178

Physicochemical interaction of oxide fuel with the cladding of the fuel elements of A fast reactor

Soviet Atomic Energy ◽

10.1007/bf01124178 ◽

1984 ◽

Vol 56 (4) ◽

pp. 207-212 ◽

Cited By ~ 2

Author(s):

V. A. Tsykanov ◽

E. F. Davydov ◽

E. P. Klochkov ◽

V. K. Shamardin ◽

V. N. Golovanov ◽

...

Keyword(s):

Fast Reactor ◽

Physicochemical Interaction ◽

Oxide Fuel ◽

Fuel Elements

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Computer code analysis of irradiation performance of axially heterogeneous mixed oxide fuel elements attaining high burnup in a fast reactor

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2019.110448 ◽

2020 ◽

Vol 359 ◽

pp. 110448

Author(s):

Tomoyuki Uwaba ◽

Keisuke Yokoyama ◽

Junichi Nemoto ◽

Ikuo Ishitani ◽

Masahiro Ito ◽

...

Keyword(s):

Fast Reactor ◽

Mixed Oxide ◽

Computer Code ◽

Oxide Fuel ◽

Code Analysis ◽

Mixed Oxide Fuel ◽

High Burnup ◽

Irradiation Performance ◽

Fuel Elements

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Thermal, radiation and mechanical analysis of cylindrical oxide fuel elements of fast reactor in unsteady state

10.31274/rtd-180814-4445 ◽

1970 ◽

Author(s):

Chi-kang Cheng

Keyword(s):

Thermal Radiation ◽

Fast Reactor ◽

Mechanical Analysis ◽

Oxide Fuel ◽

Unsteady State ◽

Fuel Elements

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Thermal, radiation and mechanical analysis of cylindrical oxide fuel elements of fast reactor in unsteady state

10.31274/rtd-180813-4445 ◽

1970 ◽

Author(s):

Chi-kang Cheng

Keyword(s):

Thermal Radiation ◽

Fast Reactor ◽

Mechanical Analysis ◽

Oxide Fuel ◽

Unsteady State ◽

Fuel Elements

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A method for determining an effective porosity correction factor for thermal conductivity in fast reactor uranium–plutonium oxide fuel pellets

Journal of Nuclear Materials ◽

10.1016/s0022-3115(00)00243-9 ◽

2000 ◽

Vol 281 (2-3) ◽

pp. 117-128 ◽

Cited By ~ 13

Author(s):

Masaki Inoue ◽

Kazuyuki Abe ◽

Isamu Sato

Keyword(s):

Thermal Conductivity ◽

Correction Factor ◽

Fast Reactor ◽

Effective Porosity ◽

Oxide Fuel ◽

Fuel Pellets ◽

Uranium Plutonium

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Application of advanced validation concepts to oxide fuel performance codes: LIFE-4 fast-reactor and FRAPCON thermal-reactor fuel performance codes

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2013.02.013 ◽

2013 ◽

Vol 263 ◽

pp. 102-128 ◽

Cited By ~ 5

Author(s):

C. Unal ◽

B.J. Williams ◽

A. Yacout ◽

D.M. Higdon

Keyword(s):

Fast Reactor ◽

Reactor Fuel ◽

Thermal Reactor ◽

Oxide Fuel ◽

Fuel Performance

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Coupled computer code study on irradiation performance of a fast reactor mixed oxide fuel element with an emphasis on the fission product cesium behavior

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2018.03.005 ◽

2018 ◽

Vol 331 ◽

pp. 186-193 ◽

Cited By ~ 2

Author(s):

Tomoyuki Uwaba ◽

Junichi Nemoto ◽

Ikuo Ishitani ◽

Masahiro Ito

Keyword(s):

Fuel Element ◽

Fission Product ◽

Fast Reactor ◽

Mixed Oxide ◽

Computer Code ◽

Oxide Fuel ◽

Mixed Oxide Fuel ◽

Irradiation Performance

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Thermal Behaviour of Xenon in a Refractory Metal for Gas Fast Reactor Fuel Elements

Defect and Diffusion Forum - Defects and Diffusion in Semiconductors X ◽

10.4028/3-908451-54-x.25 ◽

2008 ◽

pp. 25-30

Author(s):

C. Viaud ◽

G. Carlot ◽

P. Garcia ◽

P. Martin ◽

N. Millard-Pinard ◽

...

Keyword(s):

Thermal Behaviour ◽

Fast Reactor ◽

Refractory Metal ◽

Reactor Fuel ◽

Fast Reactor Fuel ◽

Fuel Elements

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Analysis of Curium in Mixed Oxide Fuel Irradiated in the Experimental Fast Reactor JOYO for the Evaluation of Its Transmutation Behavior

Journal of Nuclear Science and Technology ◽

10.1080/18811248.2004.9715563 ◽

2004 ◽

Vol 41 (9) ◽

pp. 907-914 ◽

Cited By ~ 3

Author(s):

Masahiko OSAKA ◽

Shin-ichi KOYAMA ◽

Toshiaki MITSUGASHIRA

Keyword(s):

Fast Reactor ◽

Mixed Oxide ◽

Oxide Fuel ◽

Mixed Oxide Fuel

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Behavior of mixed-oxide fuel elements during an overpower transient

Journal of Nuclear Materials ◽

10.1016/0022-3115(93)90220-s ◽

1993 ◽

Vol 204 ◽

pp. 217-227 ◽

Cited By ~ 8

Author(s):

H. Tsai ◽

L.A. Neimark ◽

T. Asaga ◽

S. Shikakura

Keyword(s):

Mixed Oxide ◽

Oxide Fuel ◽

Mixed Oxide Fuel ◽

Fuel Elements

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Evaluation of the fission gas release behavior from fast reactor mixed oxide fuel based on local concentration measurement of retained xenon

Journal of Nuclear Materials ◽

10.1016/0022-3115(88)90073-6 ◽

1988 ◽

Vol 151 (2) ◽

pp. 209-218 ◽

Cited By ~ 8

Author(s):

S. Ukai ◽

T. Hosokawa ◽

I. Shibahara ◽

Y. Enokido

Keyword(s):

Fast Reactor ◽

Mixed Oxide ◽

Concentration Measurement ◽

Local Concentration ◽

Gas Release ◽

Oxide Fuel ◽

Release Behavior ◽

Mixed Oxide Fuel ◽

Fission Gas ◽

Fission Gas Release

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