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JAEA Reports

Investigation of the core neutronics analysis conditions for evaluation of burn-up nuclear characteristics of the next-generation fast reactors

Takino, Kazuo; Oki, Shigeo

JAEA-Data/Code 2023-003, 26 Pages, 2023/05

JAEA-Data-Code-2023-003.pdf:1.66MB

Since next-generation fast reactors aim to achieve a higher core discharge burn-up than conventional reactors do, core neutronics design methods must be refined. Therefore, a suitable analysis condition is required for the analysis of burn-up nuclear characteristics to accomplish sufficient estimation accuracy while maintaining a low computational cost. We investigated the effect of the analysis conditions on the accuracy of estimation of the burn-up nuclear characteristics of next-generation fast reactors in terms of neutron energy groups, neutron transport theory, and spatial mesh. This study treated the following burn-up nuclear characteristics: criticality, burn-up reactivity, control rod worth, breeding ratio, assembly-wise power distribution, maximum linear heat rate, sodium void reactivity, and Doppler coefficient for the equilibrium operation cycle. As a result, it was found that the following conditions were the most suitable: 18-energy-group structure, 6 spatial meshes per assembly with diffusion approximation. Additionally, these conditions should apply to correction factors for energy group structure, spatial mesh and transport effects.

Journal Articles

Plasticity correction on the stress intensity factor evaluation for underclad cracks under pressurized thermal shock events

Lu, K.; Katsuyama, Jinya; Li, Y.

Proceedings of 2016 ASME Pressure Vessels and Piping Conference (PVP 2016) (Internet), 8 Pages, 2016/07

JAEA Reports

Derivation of correction factor to be applied for calculated results of PWR fuel isotopic composition by ORIGEN2 code

Suyama, Kenya; Murazaki, Minoru*; Mochizuki, Hiroki*; Nomura, Yasushi

JAERI-Tech 2001-074, 119 Pages, 2001/11

JAERI-Tech-2001-074.pdf:4.21MB

no abstracts in English

JAEA Reports

Analyses of PWR spent fuel composition using SCALE and SWAT code systems to find correction factors for criticality safety applications adopting burnup credit

Hee, S. S.*; Suyama, Kenya; Mochizuki, Hiroki*; Okuno, Hiroshi; Nomura, Yasushi

JAERI-Research 2000-066, 131 Pages, 2001/01

JAERI-Research-2000-066.pdf:6.36MB

no abstracts in English

JAEA Reports

BETA: A Code for $$beta$$$$_{eff}$$ measurement and analysis

Kato, Yuichi*; Okajima, Shigeaki; Sakurai, Takeshi

JAERI-Data/Code 99-006, 71 Pages, 1999/03

JAERI-Data-Code-99-006.pdf:3.14MB

no abstracts in English

Journal Articles

Evaluation of F-factor for delayed integral counting method

Yamane, Tsuyoshi; Takeuchi, Mitsuo; Shimakawa, Satoshi; Kaneko, Yoshihiko*

Nihon Genshiryoku Gakkai-Shi, 40(2), p.122 - 123, 1998/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

DANKE: A Monte Carlo computer program for calculating the Dancoff correction factor for spheres, rods and slabs

Okuno, Hiroshi; Komuro, Yuichi

JAERI-M 94-049, 28 Pages, 1994/03

JAERI-M-94-049.pdf:0.55MB

no abstracts in English

Journal Articles

Evaluation of local power distribution with fine-mesh core model for High Temperature Engineering Test Reactor(HTTR)

Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Shindo, Ryuichi; Fujimoto, Nozomu; Sudo, Yukio; Nakata, Tetsuo*

Journal of Nuclear Science and Technology, 31(1), p.62 - 72, 1994/01

 Times Cited Count:3 Percentile:35.79(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Anisotropic diffusion effect on criticality of plate lattice fast assembly

; Iijima, Tsutomu

Journal of Nuclear Science and Technology, 15(8), p.553 - 567, 1978/08

 Times Cited Count:0

no abstracts in English

Journal Articles

Proposal of method to estimate criticality correction for anisotropic diffusion in plate lattice fast assembly

Iijima, Tsutomu;

Journal of Nuclear Science and Technology, 14(9), p.682 - 684, 1977/09

 Times Cited Count:1

no abstracts in English

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