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Journal Articles

Assessment of calculation model for annular core on the HTTR

Nojiri, Naoki; Handa, Yuichi*; Shimakawa, Satoshi; Goto, Minoru; Kaneko, Yoshihiko*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(3), p.241 - 250, 2006/09

It was shown from the annular core experiment of the HTTR that the discrepancy of excess reactivity between experiment and analysis reached about 3 % Dk/k at maximum. Sensitivity analysis for the annular core of the HTTR was performed to improve the discrepancy. The SRAC code system was used for the core analysis. As the results of the analysis, it was found clearly that the multiplication factor of the annular core is affected by (1) mesh interval in the core diffusion calculation, (2) mesh structure of graphite region in fuel lattice cell and (3) the Benoist's anisotropic diffusion coefficients. The significantly large discrepancy previously reported was reduced down to about 1 % Dk/k by the revised annular core model.

Journal Articles

Annular core experiments in HTTR's start-up core physics tests

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

Nuclear Science and Engineering, 150(3), p.310 - 321, 2005/07

 Times Cited Count:6 Percentile:41.76(Nuclear Science & Technology)

Annular cores were formed in startup-core-physics tests of the High Temperature Engineering Test Reactor (HTTR) to obtain experimental data for verification of calculation codes. The first criticality, control rod positions at critical conditions, neutron flux distribution, excess reactivity etc. were measured as representative data. These data were evaluated with Monte Carlo code MVP that can consider the heterogeneity of coated fuel particles (CFP) distributed randomly in fuel compacts directly. It was made clear that the heterogeneity effect of CFP on reactivity for annular cores is smaller than that for fully-loaded cores. Measured and calculated effective multiplication factors (k) were agreed with differences less than 1%$$Delta$$k. Measured neutron flux distributions agreed with calculated results. The revising method was applied for evaluation of excess reactivity to exclude negative shadowing effect of control rods. The revised and calculated excess reactivity agreed with differences less than 1%$$Delta$$k/k.

Journal Articles

Start up core physics tests of High Temperature Engineering Test Reactor (HTTR), 2; First criticality by an annular form fuel loading and its criticality prediction method

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

Nihon Genshiryoku Gakkai-Shi, 42(5), p.458 - 464, 2000/05

 Times Cited Count:6 Percentile:43.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Startup core physics tests of High Temperature Engineering Test Reactor (HTTR), 1; Test plan, fuel loading and nuclear characteristics tests

Yamashita, Kiyonobu; Fujimoto, Nozomu; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*; Umeta, Masayuki; Takeda, Takeshi; Mogi, Haruyoshi; Tanaka, Toshiyuki

Nihon Genshiryoku Gakkai-Shi, 42(1), p.30 - 42, 2000/01

 Times Cited Count:3 Percentile:27.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Results of HTTR criticality tests

Fujimoto, Nozomu; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*; Yamashita, Kiyonobu; Mogi, Haruyoshi

UTNL-R-0378, p.5.1 - 5.10, 1999/00

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

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

Journal Articles

Two-phase flow pattern and heat transfer during core uncovery

Osakabe, Masahiro; Koizumi, Yasuo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 24(8), p.621 - 631, 1987/08

 Times Cited Count:8 Percentile:63.96(Nuclear Science & Technology)

no abstracts in English

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