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Journal Articles

Neutronics design for lead-bismuth cooled accelerator-driven system for transmutation of minor actinide

Tsujimoto, Kazufumi; Sasa, Toshinobu; Nishihara, Kenji; Oigawa, Hiroyuki; Takano, Hideki

Journal of Nuclear Science and Technology, 41(1), p.21 - 36, 2004/01

 Times Cited Count:144 Percentile:99.24(Nuclear Science & Technology)

Neutronics design study was performed for lead-bismuth cooled accelerator-driven system (ADS) to transmute minor actinides. Early study for ADS indicated two problems: a large burnup reactivity swing and a significant peaking factor. To solve these problems, effect of design parameters on neutronics characteristics were searched. Parametric survey calculations were performed considering fuel cycle consisting of burnup and recycle. The results showed that burnup reactivity swing depends on the plutonium fraction in the initial fuel loading, and the lead-bismuth buffer region and the two-zone loading were effective for solving the problems. Moreover, an optimum value for the effective multiplication factor was also evaluated using reactivity coefficients. From the result, the maximum allowable value of the effective multiplication factor for a practical ADS can be set at 0.97. Consequently, a new core concept combining the buffer region and the two-zone loading was proposed base on the results of the parametric survey.

Journal Articles

A Quantum reactive scattering study of the spin-forbidden CH(X$$^{2}Pi$$)+N$$_{2}$$(X$$^{1}Sigma_{g}^{+}$$)$$rightarrow $$HCN(X$$^{1}Sigma^{+}$$)+N($$^{4}$$S) reaction

Wada, Akira; Takayanagi, Toshiyuki

Journal of Chemical Physics, 116(16), p.7065 - 7072, 2002/04

 Times Cited Count:10 Percentile:30.29(Chemistry, Physical)

no abstracts in English

Journal Articles

A Design study for inherent safety core, aseismicity and heat transport system in lead-cooled nitride-fuel fast reactor

Takano, Hideki; ; ; *; *; *

Proc. of ARS94 Int. Topical Meeting on Advanced Reactors Safety,Vol. 1, 0, p.549 - 556, 1994/00

no abstracts in English

JAEA Reports

Preparation of computer codes for analyzing sensitivity coefficients of burnup characteristics

*; *; Sanda, Toshio*

PNC TJ9124 93-009, 334 Pages, 1993/03

PNC-TJ9124-93-009.pdf:7.49MB

To commertialize LMFBR, they are important subjects of research and development to improve the accuracy in neutronic design of large LMFBR cores and to make be able to design highly efficient core more rationaoy. The adjusted library has been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible by using the cross-sections adjustment method based on the probabilistic theory. And the distinct improvement of the accuracy in neutronic design of large LMFBR cores has been achieved. In the design of large LMFBR cores, however, it is important to accurately estimate not only neutronic characteristics, for example, reaction rate distribution and control rod worth but also burnup characteristics, for example, burnup reactivity loss, breeding ratio and so on. Therefore the objective of the work is to improve the prediction accuracy for burnup characteristics using many burnup data of "Joyo" effectively. For the objective computer codes for analyzing sensitivity coefficients of burnup characteristics were prepared and cross-sections adjustment using burnup data of "Joyo" was done and the effect for the improvement of the accuracy for burnup characteristics was estimated. The results are as follows: (1)The computer codes which could analyze sensitivity coefficients of burnup characteristics of LMFBR taking into consideration plural cycles and refueling were prepared and their adequacy was made sure by comparing with direct calculations. (2)It was clarified that it is possible to improve the accuracy of burnup characteristics without affecting statically neutronic characteristics so much by applying the burnup characteristics to cross-sections adjustment.

Journal Articles

A Concept of self-completed fuel cycle based on lead-cooled nitride-fuel fast reactors

Takano, Hideki; ; Handa, Nuneo; ; *; *; *; *; *; *

Proc. of the 7th Int. Conf. on Emerging Nuclear Energy Systems; ICENES 93, 8 Pages, 1993/00

no abstracts in English

Journal Articles

Effect of fission gas release on burnup characteristics and void reactivity in HCLWRs

;

Journal of Nuclear Science and Technology, 24(8), p.668 - 670, 1987/08

 Times Cited Count:0 Percentile:0.43(Nuclear Science & Technology)

no abstracts in English

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