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Journal Articles

Validation of the nuclear design code system for the HTTR using the criticality assembly VHTRC

Fujimoto, Nozomu; Nojiri, Naoki; Yamashita, Kiyonobu*

Nuclear Engineering and Design, 233(1-3), p.155 - 162, 2004/10

 Times Cited Count:3 Percentile:23.06(Nuclear Science & Technology)

The HTTR uses low-enriched uranium fuel with burnable poison rod. For validation of the nuclear design code system for the HTTR, a critical assembly of VHTRC had been constructed. The calculation uncertainties of effective multiplication factor, neutron flux distribution, burnable poison reactivity worth, and control rod worth, temperature coefficients were evaluated. Calculation accuracy of a Monte Carlo code is also evaluated.

Journal Articles

Nuclear design

Fujimoto, Nozomu; Nojiri, Naoki; Ando, Hiroei*; Yamashita, Kiyonobu*

Nuclear Engineering and Design, 233(1-3), p.23 - 36, 2004/10

 Times Cited Count:13 Percentile:62.86(Nuclear Science & Technology)

In the nuclear design of the HTTR, the reactivity balance is planned so that the design requirements are fully satisfied. Moreover, the reactivity coefficients are evaluated to confirm the safety characteristics of the reactor. The power distribution in the core was optimized by changing the uranium enrichment to maintain the fuel temperature at less than the limit (1600$$^{circ}$$C). Deviation from the optimized distribution due to the burnup of fissile materials was avoided by flattening time-dependent changes in local reactivities. Flattening was achieved by optimizing the specifications of the burnable poisons. The original nuclear design model had to be modified based on the first critical experiments. The Monte Carlo code MVP was also used to predict criticality of the initial core. The predicted excess reactivities are now in good agreement with the experimental results.

JAEA Reports

Study on nuclear physics of high burnup full MOX PWR core

Kugo, Teruhiko; Shimada, Shoichiro*; Okubo, Tsutomu; Ochiai, Masaaki

JAERI-Research 98-059, 40 Pages, 1998/10

JAERI-Research-98-059.pdf:1.73MB

no abstracts in English

JAEA Reports

Preliminary analyses for HTTR's start-up physics tests by HTTR nuclear characteristics evaluation code system

Fujimoto, Nozomu; Nojiri, Naoki; Nakano, Masaaki*; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu

JAERI-Tech 98-021, 66 Pages, 1998/06

JAERI-Tech-98-021.pdf:2.63MB

no abstracts in English

Journal Articles

The Present active status of domestic critical assemblies and the perspective for their future, 2-4; Very high temperature reactor critical assembly (VHTRC)

Akino, Fujiyoshi; Yamane, Tsuyoshi

Nihon Genshiryoku Gakkai-Shi, 40(4), p.262 - 264, 1998/00

no abstracts in English

Journal Articles

Development and valiation of nuclear design code system for High Temperature Engineering Test Reactor (HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao

The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.350 - 358, 1990/09

no abstracts in English

JAEA Reports

Design Studies for the Mark-III Core of Experimental Multi-Purpose VHTR

; ; ; ; ; ; ; Suzuki, Katsuo; ;

JAERI-M 8399, 253 Pages, 1979/08

JAERI-M-8399.pdf:5.85MB

no abstracts in English

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