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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:40.47(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.

JAEA Reports

Proposal of new $$^{235}$$U nuclear data to improve k$$_{eff}$$ biases on $$^{235}$$U enrichment and temperature for low enriched uranium fueled lattices moderated by light water

Wu, H.; Okumura, Keisuke; Shibata, Keiichi

JAERI-Research 2005-013, 31 Pages, 2005/06

JAERI-Research-2005-013.pdf:3.29MB

The under prediction of k$$_{eff}$$ depending on $$^{235}$$U enrichment in low enriched uranium fueled systems was studied in this report. Benchmark testing was carried out with several evaluated nuclear data files, including the new uranium evaluations from preliminary ENDF/B-VII and CENDL-3.1. Another problem reviewed here was k$$_{eff}$$ underestimation vs. temperature increase, which was observed in the slightly enriched system with recent JENDL and ENDF/B uranium evaluations. Through the substitute analysis of nuclear data of $$^{235}$$U and $$^{238}$$U, we propose a new evaluation of $$^{235}$$U data to solve both of the problems. The new evaluation was tested for various uranium fueled systems including low or highly enriched metal and solution benchmarks in the ICSBEP handbook. As a result, it was found that the combination of the new evaluation of $$^{235}$$U and the $$^{238}$$U data from the preliminary ENDF/B-VII gives quite good results for most of benchmark problems.

Journal Articles

Core calculation of the JMTR using MCNP

Nagao, Yoshiharu

JAERI-Conf 2000-018, p.156 - 167, 2001/01

no abstracts in English

Journal Articles

First criticality prediction of the HTTR by 1/M interposition method

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

JAERI-Conf 99-006, p.328 - 333, 1999/08

no abstracts in English

JAEA Reports

Analysis of the HTTR's benchmark problems and comparison between the HTTR and the FZJ code systems

Fujimoto, Nozomu; U.Ohlig*; H.Brockmann*; Yamashita, Kiyonobu

JAERI-Tech 98-060, 56 Pages, 1999/01

JAERI-Tech-98-060.pdf:2.25MB

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 Monte Carlo code MVP

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

JAERI-Tech 98-032, 59 Pages, 1998/08

JAERI-Tech-98-032.pdf:2.48MB

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

Benchmark problems of start-up core physics of High Temperature engineering Test Reactor (HTTR)

Yamashita, Kiyonobu; Nojiri, Naoki; Fujimoto, Nozomu; Nakano, Masaaki*; Ando, Hiroei; Nagao, Yoshiharu; Nagaya, Yasunobu; Akino, Fujiyoshi; Takeuchi, Mitsuo; Fujisaki, Shingo; et al.

Proc. of IAEA TCM on High Temperature Gas Cooled Reactor Applications and Future Prospects, p.185 - 197, 1998/00

no abstracts in English

Journal Articles

Present status of the High Temperature engineering Test Reactor(HTTR)

Tanaka, Toshiyuki; Shiozawa, Shusaku; Okubo, Minoru; Fujikawa, Seigo; Mogi, Haruyoshi; Suzuki, Hiroshi

Proceedings of European Nuclear Conference (ENC'98), 4, 5 Pages, 1998/00

no abstracts in English

Journal Articles

Delayed integral counting method for rod drop experiments

Kaneko, Yoshihiko*; Yamane, Tsuyoshi; Shimakawa, Satoshi; Yamashita, Kiyonobu

Nihon Genshiryoku Gakkai-Shi, 38(11), p.907 - 911, 1996/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Applicability of Averys coupled reactor theory to estimate subcriticality of test region in two region system

Kugo, Teruhiko

Journal of Nuclear Science and Technology, 29(6), p.513 - 520, 1992/06

no abstracts in English

Journal Articles

Reconstruction and criticality experiment in new JRR-3

Onishi, Nobuaki; Takahashi, Hidetake; Takayanagi, Masaji; Ichikawa, Hiroki; Kawasaki, Minoru

Nihon Genshiryoku Gakkai-Shi, 32(10), p.962 - 969, 1990/10

 Times Cited Count:4 Percentile:47.14(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Benchimark Calculations of the Solution-Fuel Criticality Experimentas by SRAC Code System

*; Miyoshi, Yoshinori; ;

JAERI-M 84-110, 51 Pages, 1984/06

JAERI-M-84-110.pdf:1.47MB

no abstracts in English

14 (Records 1-14 displayed on this page)
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