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JAEA Reports

Essentials of neutron multiplicity counting mathematics; An Example of U-Pu mixed dioxide

Hosoma, Takashi

JAEA-Research 2015-009, 162 Pages, 2015/08

JAEA-Research-2015-009.pdf:22.3MB

Neutron coincidence counting assay systems have been developed in the last two decades. Objects would extend to high-mass uranium-plutonium dioxide containing other spontaneous fission nuclei, so essentials of neutron multiplicity counting were reconsidered and expanded: (a) Formulae of multiplicity distribution were algebraically derived up to septuplet using a probability generating function; (b) Leakage multiplication was evaluated not by Monte Carlo method but by an average length from an arbitrary point inside a sample to an arbitrary point on its surface and a probability of induced fission within the length; (c) Mechanism of coincidence counting was associated with a couple of different time axes in Poisson process, and consequently a pair of close-to-coincident neutrons from the process was derived. For the formulae, new expressions using combination were wrote down. For spectrum and mean free path, actually treated uranium-plutonium dioxide was selected as an example.

Journal Articles

Rock-like oxide fuels and their burning in LWRs

Yamashita, Toshiyuki; Kuramoto, Kenichi; Akie, Hiroshi; Nakano, Yoshihiro; Shirasu, Noriko; Nakamura, Takehiko; Kusagaya, Kazuyuki*; Omichi, Toshihiko*

Journal of Nuclear Science and Technology, 39(8), p.865 - 871, 2002/08

 Times Cited Count:25 Percentile:16.23(Nuclear Science & Technology)

Research on the plutonium rock-like oxide (ROX) fuels and their once-through burning in light water reactors has been performed to establish an option for utilizing and disposing effectively the excess plutonium. The ROX fuel is a sort of the inert matrix fuels and consists of mineral-like compounds such as yttria stabilized zirconia, spinel and corundum. A particle-dispersed fuel was devised to reduce damage by heavy fission fragments. Some preliminary results on swelling, fractional gas release and microstructure change for five ROX fuels were obtained from the irradiation test and successive post-irradiation examinations. Inherent disadvantages of the Pu-ROX fuel cores could be improved by adding 238U or 232Th as resonant materials, and all improved cores showed a nearly the same characteristics as the conventional UO2 core during transient conditions. The threshold enthalpy of the ROX fuel rod failure was found to be comparable to the fresh UO2 rod by pulse-irradiation tests simulating reactivity initiated accident conditions.

Journal Articles

Mass spectroscopic study on the carbothermic reduction of plutonium dioxide

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Journal of Nuclear Materials, 139, p.253 - 260, 1986/00

 Times Cited Count:5 Percentile:44.59(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal coductivity of(Pu$$_{1}$$$$_{-}$$$$_{x}$$,Nd$$_{x}$$)O$$_{2}$$$$_{-}$$$$_{y}$$ and(Pu$$_{1}$$$$_{-}$$$$_{x}$$,Y$$_{x}$$)O$$_{2}$$$$_{-}$$$$_{y}$$ solid solutions

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Journal of Nuclear Materials, 115, p.118 - 127, 1983/00

 Times Cited Count:14 Percentile:19.19(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal conductivity of stoichiometric (Pu,Nd)O$$_{2}$$ and (Pu,Y)O$$_{2}$$ solid solutions

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Journal of Nuclear Materials, 114, p.260 - 266, 1983/00

 Times Cited Count:15 Percentile:19.19(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal conductivity of near-stoichiometric(U,Pu,Nd)O$$_{2}$$ and(U,Pu,Eu)O$$_{2}$$ solid solutions

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Journal of Nuclear Materials, 116, p.287 - 296, 1983/00

 Times Cited Count:28 Percentile:8.43(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Stoichiometry of fully oxidized PuO$$_{2}$$-NdO$$_{1}$$$$_{.}$$$$_{5}$$ and PuO$$_{2}$$-YO$$_{1}$$$$_{.}$$$$_{5}$$ solid solutions

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Journal of Nuclear Science and Technology, 19(8), p.681 - 683, 1982/00

 Times Cited Count:2 Percentile:55.75(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Reaction between plutonium dioxide and graphite

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Journal of Nuclear Science and Technology, 12(2), p.115 - 119, 1975/02

 Times Cited Count:5

no abstracts in English

Journal Articles

Fluorination of plutonium dioxide by fluorine

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Journal of Nuclear Science and Technology, 11(9), p.403 - 405, 1974/09

 Times Cited Count:2

no abstracts in English

Oral presentation

Examination that improves solubility of plutonium dioxide in MOX powder

Tanigawa, Masafumi; Kato, Yoshiyuki; Kurita, Tsutomu; Komatsuzaki, Mai*; Otaka, Akihiro*; Nakamichi, Hideo*

no journal, , 

no abstracts in English

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