High temperature gas-cooled reactors

Takeda, Tetsuaki*; Inagaki, Yoshiyuki; Aihara, Jun; Aoki, Takeshi; Fujiwara, Yusuke; Fukaya, Yuji; Goto, Minoru; Ho, H. Q.; Iigaki, Kazuhiko; Imai, Yoshiyuki; et al.

High Temperature Gas-Cooled Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.5, 464 Pages, 2021/02

https://doi.org/10.1016/C2018-0-05383-9

As a general overview of the research and development of a High Temperature Gas-cooled Reactor (HTGR) in JAEA, this book describes the achievements by the High Temperature Engineering Test Reactor (HTTR) on the designs, key component technologies such as fuel, reactor internals, high temperature components, etc., and operational experience such as rise-to-power tests, high temperature operation at 950C, safety demonstration tests, etc. In addition, based on the knowledge of the HTTR, the development of designs and component technologies such as high performance fuel, helium gas turbine and hydrogen production by IS process for commercial HTGRs are described. These results are very useful for the future development of HTGRs. This book is published as one of a series of technical books on fossil fuel and nuclear energy systems by the Power Energy Systems Division of the Japan Society of Mechanical Engineers.

Development of the Unattended Spent Fuel Flow Monitoring Safeguards System (UFFM) for the High Temperature Engineering Test Reactor (HTTR) (Joint research)

Nakagawa, Shigeaki; Umeda, Masayuki; Beddingfield, D. H.*; Menlove, H. O.*; Yamashita, Kiyonobu

JAEA-Technology 2007-003, 24 Pages, 2007/02

JAEA-Technology-2007-003.pdf:3.61MB

As of the safeguards approach in the HTTR facility, an unattended spent fuel flow monitor (UFFM) was applied to carry out an item counting of spent fuel blocks. The UFFM is so designed and fabricated as to be the compact and unique monitor system to verify a movement of spent fuel blocks in "difficult to access" area and reduce inspection efforts. This system consists of two detector packages, electronics and computer. One package consists of two ionization chambers and a He-3 counter. The IAEA acceptance tests were performed and it was confirmed the followings: (1) All the detectors were functioning properly to measure a spent fuel block flow. (2) The time difference between detector signals was sufficient to determine the direction of the spent fuel blocks. (3) The UFFM was useful to carry out the item counting. The UFFM was approved as the IAEA safeguards equipment in the safeguards approach in the HTTR.

Web-based search and plot system for nuclear reaction data

Otsuka, Naohiko; Aikawa, Masayuki*; Suda, Takuma*; Naito, Kenichi*; Korennov, S.*; Arai, Koji*; Noto, Hiroshi*; Onishi, Akira*; Kato, Kiyoshi*; Nakagawa, Tsuneo; et al.

AIP Conference Proceedings 769, p.561 - 564, 2005/05

https://doi.org/10.1063/1.1945071

A web-based search and plot system for nuclear reaction data has been developed, covering experimental data in EXFOR format and evaluated data in ENDF format. The system is implemented for Linux OS, with Perl and MySQL used for CGI scripts and the database manager, respectively. Two prototypes for experimental and evaluated data are presented.

Japanese evaluated nuclear data library version 3 revision-3; JENDL-3.3

Shibata, Keiichi; Kawano, Toshihiko*; Nakagawa, Tsuneo; Iwamoto, Osamu; Katakura, Junichi; Fukahori, Tokio; Chiba, Satoshi; Hasegawa, Akira; Murata, Toru*; Matsunobu, Hiroyuki*; et al.

Journal of Nuclear Science and Technology, 39(11), p.1125 - 1136, 2002/11

https://doi.org/10.3327/jnst.39.1125

Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.

Test program for NIS calibration to reactor thermal output in HTTR

Nakagawa, Shigeaki; Shinozaki, Masayuki; Tachibana, Yukio; Kunitomi, Kazuhiko

JAERI-Tech 2000-038, p.39 - 0, 2000/03

JAERI-Tech-2000-038.pdf:1.86MB

no abstracts in English

Physical design of JT-60 Super Upgrade

Nagashima, Keisuke; Kikuchi, Mitsuru; Kurita, Genichi; Ozeki, Takahisa; Aoyagi, Tetsuo; Ushigusa, Kenkichi; Neyatani, Yuzuru; Kubo, Hirotaka; Mori, Kensuke*; Nakagawa, Shoji*; et al.

Fusion Engineering and Design, 36(2-3), p.325 - 342, 1997/05

https://doi.org/10.1016/S0920-3796(96)00698-9

no abstracts in English

PROF-DD; A code system for generation of multi-group double-differential form cross section library

; Nakagawa, Masayuki;

JAERI-M 86-124, 57 Pages, 1986/08

JAERI-M-86-124.pdf:1.36MB

no abstracts in English

U.S./JAERI Fusion Neutronics Calculational Benchmarks for Nuclear Data and Codes Intercomparison

Nakagawa, Masayuki; ; *; M.Z.Youssef*; J.Jung*; M.E.Sawan*

JAERI-M 85-201, 281 Pages, 1985/12

JAERI-M-85-201.pdf:7.19MB

no abstracts in English

SLAROM:A code for cell homogenization calculation of fast reactor

Nakagawa, Masayuki;

JAERI 1294, 82 Pages, 1984/12

JAERI-1294.pdf:3.12MB

no abstracts in English

A Code System for Fast Reactor Neutronics Analysis

Nakagawa, Masayuki; *; *

JAERI-M 83-066, 74 Pages, 1983/04

JAERI-M-83-066.pdf:1.76MB

no abstracts in English