Analysis of optical density data generated from neutron radiographs of uranium-plutonium mixed oxide fuel pellets inside sealed nuclear fuel pins

Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms ◽

10.1016/0168-583x(86)90600-2 ◽

1986 ◽

Vol 14 (3) ◽

pp. 310-313 ◽

Author(s):

J.P. Panakkal ◽

J.K. Ghosh ◽

P.R. Roy

Keyword(s):

Nuclear Fuel ◽

Optical Density ◽

Mixed Oxide ◽

Density Data ◽

Mixed Oxide Fuel ◽

Fuel Pellets ◽

Uranium Plutonium

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Monitoring plutonium enrichment in mixed-oxide fuel pellets inside sealed nuclear fuel pins by neutron radiography

NDT International ◽

10.1016/0308-9126(83)90127-x ◽

1983 ◽

Vol 16 (5) ◽

pp. 275-276 ◽

Author(s):

J.K. Ghosh ◽

J.P. Panakkal ◽

P.R. Roy

Keyword(s):

Nuclear Fuel ◽

Mixed Oxide ◽

Neutron Radiography ◽

Mixed Oxide Fuel ◽

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A simple model for neutron radiography of uranium-plutonium mixed oxide fuel pins

Journal of Nuclear Materials ◽

10.1016/0022-3115(88)90196-1 ◽

1988 ◽

Vol 153 ◽

pp. 82-85 ◽

Author(s):

J.P. Panakkal ◽

J.K. Ghosh

Keyword(s):

Simple Model ◽

Mixed Oxide ◽

Neutron Radiography ◽

Mixed Oxide Fuel ◽

Uranium Plutonium

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Determination of occluded gases in mixed oxide fuel pellets using gas sampling unit and gas chromatography

Journal of Nuclear Materials ◽

10.1016/0022-3115(94)00374-2 ◽

1995 ◽

Vol 218 (1) ◽

pp. 1-7 ◽

Author(s):

T. Hiyama ◽

S. Sugaya ◽

J. Yamamoto ◽

K. Kamimura

Keyword(s):

Gas Chromatography ◽

Mixed Oxide ◽

Sampling Unit ◽

Gas Sampling ◽

Mixed Oxide Fuel ◽

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Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2

10.3403/30254332u ◽

2015 ◽

Keyword(s):

Nitric Acid ◽

Mixed Oxide ◽

Mixed Oxide Fuel ◽

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Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2

10.3403/30254332 ◽

2018 ◽

Keyword(s):

Nitric Acid ◽

Mixed Oxide ◽

Mixed Oxide Fuel ◽

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Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor

Journal of Nuclear Materials ◽

10.1016/j.jnucmat.2008.12.028 ◽

2009 ◽

Vol 385 (2) ◽

pp. 407-412 ◽

Author(s):

Kosuke Tanaka ◽

Shuhei Miwa ◽

Isamu Sato ◽

Takashi Hirosawa ◽

Hiroshi Obayashi ◽

...

Keyword(s):

Fast Reactor ◽

Mixed Oxide ◽

Elemental Distribution ◽

Mixed Oxide Fuel ◽

Irradiation Test ◽

Uranium Plutonium

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A simple model for neutron radiography of uranium-plutonium mixed oxide fuel pins

NDT International ◽

10.1016/0308-9126(89)91040-7 ◽

1989 ◽

Vol 22 (4) ◽

pp. 243

Keyword(s):

Simple Model ◽

Mixed Oxide ◽

Neutron Radiography ◽

Mixed Oxide Fuel ◽

Uranium Plutonium

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Creep of Mixed-Oxide Fuel Pellets at High Stress

Journal of the American Ceramic Society ◽

10.1111/j.1151-2916.1973.tb12507.x ◽

1973 ◽

Vol 56 (6) ◽

pp. 330-333 ◽

Author(s):

J. L. ROUTBORT ◽

J. C. VOGLEWEDE

Keyword(s):

Mixed Oxide ◽

High Stress ◽

Mixed Oxide Fuel ◽

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Determination of nitrogen in uranium-plutonium mixed oxide fuel by gas chromatography after fusion in an inert gas atmosphere

Analytica Chimica Acta ◽

10.1016/s0003-2670(97)00109-8 ◽

1997 ◽

Vol 345 (1-3) ◽

pp. 131-137 ◽

Author(s):

Toshiaki Hiyama ◽

Toshio Takahashi ◽

Katsuichiro Kamimura

Keyword(s):

Gas Chromatography ◽

Mixed Oxide ◽

Inert Gas ◽

Mixed Oxide Fuel ◽

Gas Atmosphere ◽

Uranium Plutonium

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Compressive creep of mixed-oxide fuel pellets

Journal of Nuclear Materials ◽

10.1016/0022-3115(72)90036-0 ◽

1972 ◽

Vol 44 (3) ◽

pp. 247-259 ◽

Author(s):

J.L Routbort ◽

N.A Javed ◽

J.C Voglewede

Keyword(s):

Mixed Oxide ◽

Compressive Creep ◽

Mixed Oxide Fuel ◽

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