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Journal Articles

Optimization of seed-blanket type fuel assembly for reduced-moderation water reactor

Shelley, A.; Shimada, Shoichiro*; Kugo, Teruhiko; Okubo, Tsutomu; Iwamura, Takamichi

Nuclear Engineering and Design, 224(3), p.265 - 278, 2003/10

 Times Cited Count:15 Percentile:67.36(Nuclear Science & Technology)

Parametric studies have been done for a PWR-type reduced-moderation water reactor (RMWR) with seed-blanket fuel assembles to achieve a high conversion ratio, negative void reactivity coefficient and a high burnup. It was found that 50 to 60% of seed in a seed-blanket assembly has higher conversion ratio. The number of seed-blanket layers is 20, in which the number of seed layers is 15 and blanket layers is 5. The fuel assembly with the height of seed of 1000mm$$times$$2, internal blanket of 150 mm and axial blanket of 400mm$$times$$2 is recommended. The conversion ratio is 1.0 and the average burnup in core region is 38.2 GWd/t. The enrichment of fissile Pu is 14.6 wt%. The void coefficient is +21.8 pcm/% void, however, it is expected that the void coefficient will be negative if the radial neutron leakage is taken into account. It is also possible to use this fuel assembly for a high core averaged burnup of 45GWd/t, however, the height of seed must be 500mm$$times$$2 to improve the void coefficient. The conversion ratio is 0.97 and void coefficient is +20.8 pcm/%void.

Journal Articles

Advanced concept of Reduced-Moderation Water Reactor (RMWR) for plutonium multiple recycling

Okubo, Tsutomu; Takeda, Renzo*; Iwamura, Takamichi; Yamamoto, Kazuhiko*; Okada, Hiroyuki*

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 7 Pages, 2001/09

An advanced water-cooled reactor concept named the Reduced-Moderation Water Reactor (RMWR) has been proposed to attain a high conversion ratio more than 1.0 and to achieve the negative void reactivity coefficient. At present, several types of design concepts satisfying both the design targets have been proposed based on the evaluation for the fuel without fission products and minor actinides. In this paper, the feasibility of the RMWR core is investigated and confirmed for the plutonium multiple recycling under advanced reprocessing schemes with low decontamination factors as proposed for the FBR fuel cycle.

Journal Articles

Experimental verification and analysis of neutron streaming effect through void holes for control rod insertion in HTTR

Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko

Journal of Nuclear Science and Technology, 34(2), p.185 - 192, 1997/02

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Accuracy of cell calculation methods used for analysis of high conversion light water lattice

C-J.Jeong*; Okumura, Keisuke; ; Tanaka, Kenichi*

Journal of Nuclear Science and Technology, 27(6), p.515 - 523, 1990/06

no abstracts in English

JAEA Reports

Benchmark Calculation on Nuclear Characteristics of JRR-4 HZU Core by SRAC Code System

Arigane, Kenji

JAERI-M 87-063, 133 Pages, 1987/04

JAERI-M-87-063.pdf:3.46MB

no abstracts in English

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