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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

 Percentile:100(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

Reactivity estimation using digital nonlinear H$$_{infty}$$ estimator for VHTRC experiment

Suzuki, Katsuo; Nabeshima, Kunihiko; Yamane, Tsuyoshi; Fujii, Yoshio*

Nippon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.408 - 417, 2003/12

On-line and real-time estimation of time-varying reactivity in a nuclear reactor is necessary for early detection of reactivity anomaly and safe operation. Using a digital nonlinear H$$infty$$ estimator, an experiment of real-time dynamic reactivity estimation was carried out in the VHTRC of JAERI. Some technical issues of the experiment are described, such as reactivity insertion, data sampling frequency, anti-aliasing filter, experimental circuit and digitalizing nonlinear H$$infty$$ reactivity estimator, and so on. Then, we discussed the experimental results obtained by the digital nonlinear H$$infty$$ estimator with sampled data of the nuclear instrumentation signal for the power responses under various reactivity insertions. Good performances of estimated reactivity were observed, with almost no delay to the true reactivity and sufficient accuracy between 0.05cent and 0.1cent. From the results of the experiment, it is concluded that the digital nonlinear H$$infty$$ reactivity estimator can be applied as on-line real-time reactivity meter for actual nuclear plants.

Journal Articles

Evaluation of Delayed Neutron Data for JENDL-3.3

Yoshida, Tadashi*; Okajima, Shigeaki; Sakurai, Takeshi; Nakajima, Ken; Yamane, Tsuyoshi; Katakura, Junichi; Tahara, Yoshihisa*; Zukeran, Atsushi*; Oyamatsu, Kazuhiro*; Osawa, Takaaki*; et al.

Journal of Nuclear Science and Technology, 39(Suppl.2), p.136 - 139, 2002/08

no abstracts in English

Journal Articles

Decommissioning of VHTRC

Takeuchi, Motoyoshi; Nakajima, Katsutoshi; Fukumura, Nobuo*; Nakayama, Fusao*; Ohori, Hideshi*

Dekomisshoningu Giho, (24), p.27 - 46, 2001/09

no abstracts in English

Journal Articles

Summary of dismantling project of a critical assembly, VHTRC

Yasuda, Hideshi

RANDEC Nyusu, (45), p.6 - 7, 2000/05

no abstracts in English

JAEA Reports

Study of burnable absorber reactivity worth evaluation method considering the position of burnable absorber rod in a block using VHTRC experimental results

Fujimoto, Nozomu; Yamashita, Kiyonobu; Akino, Fujiyoshi

JAERI-Research 99-052, p.51 - 0, 1999/09

JAERI-Research-99-052.pdf:2.05MB

no abstracts in English

Journal Articles

Measurement of control rod reactivity worth with long insertion time by inverse kinetics rod drop method

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

Nippon Genshiryoku Gakkai-Shi, 41(1), p.35 - 38, 1999/00

 Percentile:100(Nuclear Science & Technology)

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

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

no abstracts in English

JAEA Reports

Evaluation of accuracy of Monte Carlo code MVP with VHTRC experiments; Multiplication factor at criticality, burnable poison worth and void worth

Nojiri, Naoki; Yamashita, Kiyonobu; Fujimoto, Nozomu; Nakano, Masaaki*; Yamane, Tsuyoshi; Akino, Fujiyoshi

JAERI-Tech 97-060, 34 Pages, 1997/11

JAERI-Tech-97-060.pdf:1.08MB

no abstracts in English

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

 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of the high temperature engineering test reactor's first criticality with Monte Carlo code

Yamashita, Kiyonobu; Ando, Hiroei; Nojiri, Naoki; Fujimoto, Nozomu; Nakata, Tetsuo*; Watanabe, Takashi*; Yamane, Tsuyoshi; Nakano, Masaaki*

Proc. of SARATOGA 1997, 2, p.1557 - 1566, 1997/00

no abstracts in English

JAEA Reports

VHTRC experiment for verification test of H$$infty$$ reactivity estimation method

Fujii, Yoshio; Suzuki, Katsuo; Akino, Fujiyoshi; Yamane, Tsuyoshi; Fujisaki, Shingo; Takeuchi, Motoyoshi; Ono, Toshihiko

JAERI-Data/Code 96-001, 102 Pages, 1996/02

JAERI-Data-Code-96-001.pdf:2.32MB

no abstracts in English

Journal Articles

Nuclear design of the high-temperature engineering test reactor (HTTR)

Yamashita, Kiyonobu; ; Murata, Isao; Maruyama, So; Fujimoto, Nozomu; Takeda, Takeshi

Nuclear Science and Engineering, 122, p.212 - 228, 1996/00

 Times Cited Count:22 Percentile:13.14(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of control rod reactivity worth in axially heterogeneous fuel core (VHTRC-4) by PNS method

Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko; Fujisaki, Shingo

PHYSOR 96: Int. Conf. on the Physics of Reactors, 2, p.E281 - E289, 1996/00

no abstracts in English

Journal Articles

Temperature effect on critical mass and kinetic parameter $$beta$$$$_{eff}$$/$$wedge$$ of VHTRC-4 core

Yamane, Tsuyoshi; Akino, Fujiyoshi;

PHYSOR 96: Int. Conf. on the Physics of Reactors, 2, p.E290 - E299, 1996/00

no abstracts in English

JAEA Reports

Compilation report of VHTRC temperature coefficient benchmark calculations

; Yamane, Tsuyoshi

JAERI-Research 95-081, 32 Pages, 1995/11

JAERI-Research-95-081.pdf:1.28MB

no abstracts in English

JAEA Reports

VHTRC temperature coefficient benchmark problem

; Yamane, Tsuyoshi; Sasa, Toshinobu

JAERI-Data/Code 94-013, 17 Pages, 1994/10

JAERI-Data-Code-94-013.pdf:0.77MB

no abstracts in English

Journal Articles

Measurement of effective delayed neutron fraction of VHTRC-1 core

Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko

Journal of Nuclear Science and Technology, 31(8), p.861 - 863, 1994/08

 Times Cited Count:2 Percentile:61.76(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of overall temperature coefficient of reactivity of the VHTRC-1 core with a nuclear design code system for the High-Temperature Engineering Test Reactor

Yamashita, Kiyonobu; Murata, Isao;

Nuclear Science and Engineering, 110, p.177 - 185, 1992/02

 Times Cited Count:3 Percentile:45.52(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of overall temperature coefficient of reactivity of VHTRC-1 core by pulsed neutron method

Yamane, Tsuyoshi; ; Akino, Fujiyoshi; Kaneko, Yoshihiko

Journal of Nuclear Science and Technology, 27(2), p.122 - 132, 1990/02

no abstracts in English

22 (Records 1-20 displayed on this page)