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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

An Investigation into dissolution rate of spent nuclear fuel in aqueous reprocessing

Mineo, Hideaki; Isogai, Hikaru; Morita, Yasuji; Uchiyama, Gunzo*

Journal of Nuclear Science and Technology, 41(2), p.126 - 134, 2004/02

 Times Cited Count:5 Percentile:37.08(Nuclear Science & Technology)

A simple equation was proposed for the dissolution rate of spent LWR fuel, of which the change in the dissolution area was estimated by taking into account of the area of the cracks occurring due to thermal shrinkage of the pellets during irradiation. The applicability of proposed equation was examined using LWR fuel dissolution test results in the present study as well as the results obtained by other workers. The equation showed good agreements with the dissolution test results obtained from spent fuel pellets and pulverized spent fuel. It was indicated that the proposed equation was simple and would be useful for the prediction of dissolution of spent LWR fuels. However, the initial effective dissolution area, the parameter of the equation, was found to depend on the temperature, which could not be explained by the proposed equation. Further studies on the role of other factors affecting dissolution rate, such as nitrous acid, in the dissolution of spent fuel was required.

Journal Articles

Investigation of vaporization behavior of hyper-stoichiometric uranium dioxide by Knudsen effusion mass spectrometry

Nakajima, Kunihisa; Arai, Yasuo

Journal of Nuclear Materials, 317(2-3), p.243 - 251, 2003/05

 Times Cited Count:3 Percentile:26.73(Materials Science, Multidisciplinary)

The Knudsen effusion mass-spectrometric measurement of pure UO$$_{2+x}$$(s) are carried out at 1673, 1773 and 1873K to evaluate $$Delta$$G$$_{f}$$$$^{circ}$$(UO$$_{3}$$,g) as well as to measure the partial pressures of UO$$_{3}$$(g) and O$$_{2}$$(g) over UO$$_{2+x}$$(s) as function of the O/U ratio. It was found that the partial pressures of O$$_{2}$$(g) over UO$$_{2+x}$$(s) almost agree with the experimental data reported in the past and the values derived from the empirical equation given by Nakamura and Fujino. Further, it was found that the values of $$Delta$$G$$_{f}$$$$^{circ}$$(UO$$_{3}$$,g) obtained in this study are in good agreement with the recommended values.

Journal Articles

Heat capacity measurements on unirradiated and irradiated fuel pellets

Amaya, M.*; Une, Katsumi*; Minato, Kazuo

Journal of Nuclear Materials, 294(1-2), p.1 - 7, 2001/04

 Times Cited Count:12 Percentile:66.38(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal conductivities of irradiated UO$$_{2}$$ and (U,Gd)O$$_{2}$$

Minato, Kazuo; Shiratori, Tetsuo; Serizawa, Hiroyuki; Hayashi, Kimio; Une, Katsumi*; Nogita, Kazuhiro*; Hirai, Mutsumi*; Amaya, M.*

Journal of Nuclear Materials, 288(1), p.57 - 65, 2001/01

 Times Cited Count:19 Percentile:79.57(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effects of grain size and PCI restraint on the rim structure formation of UO$$_{2}$$ fuels

Une, Katsumi*; Nogita, Kazuhiro*; Suzaka, Yojiro*; Hayashi, Kimio; Ito, Kunio*; Eto, Yoshinori*

International Topical Meeting on Light Water Reactor Fuel Performance, 2, p.775 - 785, 2000/00

no abstracts in English

Journal Articles

Radiation damage in UO$$_{2}$$ bombarded with iodine and nickel ions at energies around 100 MeV

Hayashi, Kimio; ; Fukuda, Kosaku

Advances in Science and Technology, 24, p.439 - 446, 1999/00

no abstracts in English

Journal Articles

Nonuniformity effect on reactivity of fuel in slurry

; *

Nuclear Technology, 122(3), p.265 - 275, 1998/00

 Times Cited Count:1 Percentile:15.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Radiation damage of UO$$_{2}$$ by high-energy heavy ions

Hayashi, Kimio; ; Fukuda, Kosaku

Journal of Nuclear Materials, 248, p.191 - 195, 1997/00

 Times Cited Count:17 Percentile:78.56(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Non-uniformity effect on reactivity of fuel in slurry

Okuno, Hiroshi; *

PHYSOR 96: Int. Conf. on the Physics of Reactors, 4, p.L74 - L82, 1996/00

no abstracts in English

JAEA Reports

Calculations for reflector savings of steel and stainless steel

*; Okuno, Hiroshi

JAERI-Research 94-047, 39 Pages, 1994/12

JAERI-Research-94-047.pdf:0.89MB

no abstracts in English

JAEA Reports

Analyses with MCNP code of the criticality experiment of pellet-solution coexisting low-enriched uranium fuel

*; Arakawa, Takuya*; Okuno, Hiroshi

JAERI-Data/Code 94-018, 36 Pages, 1994/12

JAERI-Data-Code-94-018.pdf:1.09MB

no abstracts in English

JAEA Reports

Journal Articles

Performance of ZrC-coated particle fuel in irradiation and postirradiation heating tests

Ogawa, Toru; Fukuda, Kosaku; Kashimura, Satoru; Tobita, Tsutomu; Kobayashi, Fumiaki; ; ; ; Kikuchi, Teruo

Journal of the American Ceramic Society, 75(11), p.2985 - 2990, 1992/11

 Times Cited Count:38 Percentile:84.46(Materials Science, Ceramics)

no abstracts in English

Journal Articles

Effect of fuel grain size on reactivity

Okuno, Hiroshi; Naito, Yoshitaka; Sakurai, Y.*

Journal of Nuclear Science and Technology, 28(10), p.958 - 960, 1991/10

no abstracts in English

JAEA Reports

Effects of UO$$_{2}$$ fuel grain size on reactivity; Continuous energy Monte Carlo calculations

Sakurai, Y.*; Okuno, Hiroshi; Naito, Yoshitaka

JAERI-M 91-137, 35 Pages, 1991/09

JAERI-M-91-137.pdf:0.88MB

no abstracts in English

JAEA Reports

Migration behavior of palladium in UO$$_{2}$$

*; Ohashi, Hiroshi*; Morozumi, Takashi *; Ogawa, Toru; Fukuda, Kosaku

JAERI-M 90-113, 46 Pages, 1990/07

JAERI-M-90-113.pdf:3.74MB

no abstracts in English

Journal Articles

Electrical conductivity of oxygen deficient urania-yttria solid solutions

; ; ;

Journal of Nuclear Materials, 151, p.90 - 94, 1987/00

 Times Cited Count:3 Percentile:76.03(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Out-pile FP Release Experiment by Heating of Irradiated UO$$_{2}$$ Pellet

;

JAERI-M 85-199, 16 Pages, 1985/12

JAERI-M-85-199.pdf:0.68MB

no abstracts in English

31 (Records 1-20 displayed on this page)