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JAEA Reports

Preliminary study on HTTR tests for development of commercial HTGRs

Goto, Minoru; Takamatsu, Kuniyoshi; Nakagawa, Shigeaki; Ueta, Shohei; Hamamoto, Shimpei; Ohashi, Hirofumi; Furusawa, Takayuki; Saito, Kenji; Shimazaki, Yosuke; Nishihara, Tetsuo

JAEA-Technology 2009-053, 48 Pages, 2009/10

JAEA-Technology-2009-053.pdf:3.41MB

Preliminary studies on the HTTR (High Temperature engineering Test Reactor) tests were conducted to obtain characteristics and demonstration data which were required to develop commercial HTGRs (high temperature gas-cooled reactors). The tests proposed in this study are as follows: nuclear heat supply characteristics tests, burned core tests, reactivity insertion tests, safety demonstration tests, fuel characteristics tests, annular core tests, fuel failure tests, tritium measurement tests, and health confirmation tests of high temperature equipments. Requirements for a development of commercial HTGRs and confirmation methods of the requirements by the HTTR tests were summarized. Preliminary analyses were performed for the burned core test and the safety demonstration test to obtain prediction data, which is compared with experimental data. Additionally, a feasibility analysis was performed on four types annular cores, which is composed of the HTTR's fresh fuels, from the point of view of shutdown margin and excess reactivity.

JAEA Reports

Safety demonstration test (SR-2/S2C-2/SF-1) plan using the HTTR (Contract research)

Sakaba, Nariaki; Nakagawa, Shigeaki; Takamatsu, Kuniyoshi; Takada, Eiji*; Saito, Kenji; Furusawa, Takayuki; Tochio, Daisuke; Tachibana, Yukio; Iyoku, Tatsuo

JAERI-Tech 2004-014, 24 Pages, 2004/02

JAERI-Tech-2004-014.pdf:1.06MB

Safety demonstration tests using the HTTR are in progress to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to not only the commercial HTGRs but also the research and development for the VHTR one of the Generation IV reactors. This paper describes the reactivity insertion test and coolant flow reduction test by trip of gas circulator and partial flow loss of coolant planned in 2004 with detailed test method, procedure and results of pre-test analysis. From the analytical results, it was found that the negative reactivity feedback effect of the core brings the reactor power safely to a stable level without a reactor scram.

JAEA Reports

Safety demonstration test (S1C-2/S2C-1) plan using the HTTR (Contract research)

Sakaba, Nariaki; Nakagawa, Shigeaki; Takada, Eiji*; Tachibana, Yukio; Saito, Kenji; Furusawa, Takayuki; Takamatsu, Kuniyoshi; Tochio, Daisuke; Iyoku, Tatsuo

JAERI-Tech 2003-074, 37 Pages, 2003/08

JAERI-Tech-2003-074.pdf:1.83MB

Safety demonstration tests using HTTR are now underway in order to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to research and development for the VHTR, which is one of the Generation IV reactors. The first phase of the safety demonstration tests includes reactivity insertion tests by means of control-rod withdrawal and coolant flow reduction tests by tripping the gas circulators. In the second phase, accident simulation tests will be conducted. This paper describes the plan of coolant flow reduction tests by tripping of gas circulators planned in August 2003 with detailed test method, procedure and results of pre-test analysis. The analysis results of the steady state and transient behaviours of the reactor and the plant of the HTTR show that in the case of a rapid decrease of the coolant flow rate, the negative reactivity feedback effect of the core brings the reactor power safely to certain stable level without a reactor scram, and that the temperature transient of the reactor core is slow.

JAEA Reports

Findings of the reactor automatic shutdown caused by a signal of a primary coolant flow rate of the PPWC:Low in the HTTR

Takamatsu, Kuniyoshi; Nakazawa, Toshio; Furusawa, Takayuki; Homma, Fumitaka; Saito, Kenji; Kokusen, Shigeru; Kamata, Takashi; Ota, Yukimaru; Ishii, Yoshiki; Emori, Koichi

JAERI-Tech 2003-062, 94 Pages, 2003/06

JAERI-Tech-2003-062.pdf:26.47MB

no abstracts in English

Oral presentation

Development and validation of analytical methodology regarding reactor performance and safety characteristics of HTGR, 1; Project overview

Takeda, Tetsuaki; Nakagawa, Shigeaki; Goto, Minoru; Takamatsu, Kuniyoshi; Saito, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Evaluation of radioactivity inventory in the Fugen, 12; Development of activation activity evolution system (ORIGEN-2) for Fugen

Kitamura, Koichi; Tanji, Kazuhiro*; Morishita, Yoshitsugu; Hayashi, Hirokazu; Yamaguchi, Katsuyoshi*; Saito, Kuniyoshi*

no journal, , 

no abstracts in English

Oral presentation

Development and validation of analytical methodology regarding reactor performance and safety characteristics of HTGR, 5; Reactor transients during coolant flow reduction events

Takamatsu, Kuniyoshi; Saito, Hiroyuki; Nakagawa, Shigeaki; Takeda, Tetsuaki

no journal, , 

no abstracts in English

Oral presentation

Analysis on reactor performance and safety characteristics of HTGR, 3; Development and validation of analytical methodology for reactor kinetics

Takamatsu, Kuniyoshi; Takeda, Tetsuaki; Nakagawa, Shigeaki; Goto, Minoru; Saito, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Analysis on reactor performance and safety characteristics of HTGR, 4; Test plan of simulating loss of coolant flow event by using HTTR

Nakagawa, Shigeaki; Takamatsu, Kuniyoshi; Takeda, Tetsuaki; Goto, Minoru; Saito, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Analysis on reactor performance and safety characteristics of HTGR, 1; Project overview of development and validation of analytical methods

Takeda, Tetsuaki; Nakagawa, Shigeaki; Goto, Minoru; Takamatsu, Kuniyoshi; Saito, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

Analysis on reactor performance and safety characteristics of HTGR, 2; Nuclear characteristics

Goto, Minoru; Takamatsu, Kuniyoshi; Takeda, Tetsuaki; Nakagawa, Shigeaki; Saito, Hiroyuki

no journal, , 

no abstracts in English

11 (Records 1-11 displayed on this page)
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