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Journal Articles

Development plan for coupling technology between high temperature gas-cooled reactor HTTR and hydrogen production facility, 1; Overview of the HTTR heat application test plan to establish high safety coupling technology

Nomoto, Yasunobu; Mizuta, Naoki; Morita, Keisuke; Aoki, Takeshi; Okita, Shoichiro; Ishii, Katsunori; Kurahayashi, Kaoru; Yasuda, Takanori; Tanaka, Masato; Isaka, Kazuyoshi; et al.

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 7 Pages, 2023/05

Journal Articles

Release behavior of Cs and its chemical form during late phase of Fukushima Daiichi Nuclear Power Plant accident

Hidaka, Akihide; Yokoyama, Hiroya

Proceedings of Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2017 (AWC 2017) (USB Flash Drive), p.29 - 42, 2017/09

no abstracts in English

Journal Articles

Altitude control performance improvement via preview controller for unmanned airplane for radiation monitoring system

Sato, Masayuki*; Muraoka, Koji*; Hozumi, Koki*; Sanada, Yukihisa; Yamada, Tsutomu*; Torii, Tatsuo

Nihon Koku Uchu Gakkai Rombunshu (Internet), 65(2), p.54 - 63, 2017/02

This paper is concerned with the design problem of preview altitude controller for Unmanned Airplane for Radiation Monitoring System (UARMS) to improve its control performance. UARMS has been developed for radiation monitoring around Fukushima Daiichi Nuclear Power Plant which spread radiation contaminant due to the huge tsunamis caused by the Great East Japan Earthquake. The monitoring area contains flat as well as mountain areas. The basic flight controller has been confirmed to have satisfactory performance with respect to altitude holding; however, the control performance for variable altitude commands is not sufficient for practical use in mountain areas. We therefore design preview altitude controller with only proportional gains by considering the practicality and the strong requirement of safety for UARMS. Control performance of the designed preview controller was evaluated by flight tests conducted around Fukushima Sky Park.

Journal Articles

Pre-test analysis method using a neural network for control-rod withdrawal tests of HTTR

Ono, Tomio*; Subekti, M.*; Kudo, Kazuhiko*; Takamatsu, Kuniyoshi; Nakagawa, Shigeaki; Nabeshima, Kunihiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(2), p.115 - 126, 2005/06

Control-rod withdrawal tests simulating reactivity insertion are carried out in the HTTR to verify the inherent safety features of HTGRs. This paper describes pre-test analysis method using artificial neural networks to predict the changes of reactor power and reactivity. The network model applied in this study is based on recurrent neural networks. The inputs of the network are the changes of the central control rods position and other significant core parameters, and the outputs are the changes of reactor power and reactivity. Furthermore, Time Synchronizing Signal(TSS) is added to input to improve the modeling of time series data. The actual tests data, which were previously carried out in the HTTR, were used for learning the model of the plant dynamics. After the learning, the network can predict the changes of reactor power and reactivity in the following tests.

Journal Articles

Development of supercritical pressure water cooled solid breeder blanket in JAERI

Akiba, Masato; Ishitsuka, Etsuo; Enoeda, Mikio; Nishitani, Takeo; Konishi, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.929 - 934, 2003/09

no abstracts in English

JAEA Reports

Test plans of the high temperature test operation at HTTR

Sakaba, Nariaki; Nakagawa, Shigeaki; Takada, Eiji*; Nojiri, Naoki; Shimakawa, Satoshi; Ueta, Shohei; Sawa, Kazuhiro; Fujimoto, Nozomu; Nakazawa, Toshio; Ashikagaya, Yoshinobu; et al.

JAERI-Tech 2003-043, 59 Pages, 2003/03

JAERI-Tech-2003-043.pdf:2.54MB

HTTR plans a high temperature test operation as the fifth step of the rise-to-power tests to achieve a reactor outlet coolant temperature of 950 degrees centigrade in the 2003 fiscal year. Since HTTR is the first HTGR in Japan which uses coated particle fuel as its fuel and helium gas as its coolant, it is necessary that the plan of the high temperature test operation is based on the previous rise-to-power tests with a thermal power of 30 MW and a reactor outlet coolant temperature at 850 degrees centigrade. During the high temperature test operation, reactor characteristics, reactor performances and reactor operations are confirmed for the safety and stability of operations. This report describes the evaluation result of the safety confirmations of the fuel, the control rods and the intermediate heat exchanger for the high temperature test operation. Also, problems which were identified during the previous operations are shown with their solution methods. Additionally, there is a discussion on the contents of the high temperature test operation. As a result of this study, it is shown that the HTTR can safely achieve a thermal power of 30MW with the reactor outlet coolant temperature at 950 degrees centigrade.

JAEA Reports

Development of ultrasonic heat transfer tube thickness measurement apparatus (Contract research)

Oba, Toshihiro; Suetsugu, Hidehiko*; Yano, Masaya*; Kato, Chiaki; Yanagihara, Takao

JAERI-Tech 2002-082, 47 Pages, 2003/01

JAERI-Tech-2002-082.pdf:1.87MB

The demonstration test for evaluating reliability of the acid recovery evaporator at Rokkasho Reprocessing Plant has been carried out at JAERI. For the nondestructive measurement of the thickness of heat transfer tubes of the acid recovery evaporator in corrosion test, we have developed thickness measurement apparatus for heat transfer tubes by ultrasonic immersion method with high resolution. The ultrasonic prove in a heat transfer tube can be moved vertically and radially. The results obtained by this apparatus coincident well with those obtained by a destructive method using an optical microscope.

JAEA Reports

Analytical evaluation on loss of off-site electric power simulation of the High Temperature Engineering Test Reactor

Takeda, Takeshi; Nakagawa, Shigeaki; Tachibana, Yukio; Takada, Eiji*; Kunitomi, Kazuhiko

JAERI-Research 2000-016, p.80 - 0, 2000/03

JAERI-Research-2000-016.pdf:2.72MB

no abstracts in English

Journal Articles

Radiation effects and safety control of tritium, 2; Status of tritium use and source term

Noguchi, Hiroshi

Nihon Genshiryoku Gakkai-Shi, 39(11), p.915 - 916, 1997/00

no abstracts in English

JAEA Reports

NRTA data processing system: PROMAC-J

Ikawa, Koji; Ihara, Hitoshi; Nishimura, Hideo

JAERI-M 93-182, 160 Pages, 1993/09

JAERI-M-93-182.pdf:3.31MB

no abstracts in English

JAEA Reports

Demonstration test on the safety of a cell ventilation system during a hypothetical explosive burning in a fuel reprocessing plant

Suzuki, Motoe; Nishio, Gunji; Takada, Junichi; Tsukamoto, Michio; Koike, Tadao

JAERI 1328, 90 Pages, 1993/01

JAERI-1328.pdf:4.24MB

no abstracts in English

Journal Articles

Tritium Process Laboratory at the JAERI

Naruse, Yuji; Matsuda, Yuji; *

Fusion Engineering and Design, 12, p.293 - 317, 1990/00

 Times Cited Count:78 Percentile:98.31(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of a near real time materials accountancy data processing system and evaluation of statistical analysis methods using field test data

; ; ; *; *; *

Nuclear Safeguards Technology 1986,Vol.1, p.341 - 352, 1987/00

no abstracts in English

Journal Articles

A Near-real-time materials accountancy model and its preliminary demonstration in Tokai reprocessing plant

; ; ; *; *

Nuclear Safeguards Technology,Vol.1, p.499 - 512, 1983/00

no abstracts in English

Journal Articles

Investigation of sample plan for safeguards verification activities

; ; ; *; *

Nuclear Safeguards Technology,Vol.2, p.317 - 330, 1983/00

no abstracts in English

JAEA Reports

Technical Development of Computer Control of OWL-0

;

JAERI-M 5844, 155 Pages, 1974/09

JAERI-M-5844.pdf:4.74MB

no abstracts in English

Journal Articles

Airborne iodine monitoring at the radioisotope test production plant, JAERI

; ; ;

Proc.1st Intern.Cong.of Radiation Protection,Rome, p.1153 - 1166, 1966/09

no abstracts in English

17 (Records 1-17 displayed on this page)
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