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Journal Articles

Development of dual arm manipulators with remote control system

Tachibana, Mitsuo; Shimada, Taro; Yanagihara, Satoshi

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.489 - 492, 2002/06

A remote dismantling robot was developed for decommissioning in nuclear facilities. The remote dismantling robot consists of two electrical powered manipulators, end-effectors and a control system. To realize stable dismantling operation remotely, the remote dismantling robot is designed from view point of proper control in coping with different activity conditioning by feedback of image and of force to the control system. The image feedback was considered to obtain accurate positioning of the end-effectors and the force feedback was considered to supply proper force for direct interaction with an object. Motion tests were performed to verify the remote dismantling robot and its control system. As a result, it was confirmed that the remote dismantling activities such as cutting, radioactivity measurement, decontamination were conducted efficiently by using the image feedback and the force feedback.

Journal Articles

Current status of study on fuel-coolant interactions (FCIs) relevant to LWR severe accidents

Moriyama, Kiyofumi; Nakamura, Hideo; Hirano, Masashi

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.209 - 214, 2002/06

Through a review of experimental works on steam explosions and consideration on the uncertainty in the methodology for plant scale analysis of each stage of the phenomena, it was identified that the molten jet breakup process in premixing has an important uncertainty caused by lack of experimental knowledge. Based on this perspective, an experimental work are under planning at Japan Atomic Energy Research Institute (JAERI), in which the premixing stage of steam explosions in a deep water pool is modeled by high temperature oxide melts. Melt material and scale of the experiment were examined in terms of the simulation capability of the jet breakup mechanism in a plant scale phenomena. Materials and geometrical scale considered adequate were found.

Journal Articles

Research on safety systems for future reactors using the ROSA/LSTF facility

Yonomoto, Taisuke; Otsu, Iwao; Nakamura, Hideo; Kondo, Masaya; Svetlov, S.*

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.215 - 220, 2002/06

no abstracts in English

Journal Articles

Research and development in JNC on geological isolation of high-level radioactive waste in the implementation phase of disposal

Igarashi, Hiroshi; Aoki, Kazuhiro; Miyahara, Kaname; Shiotsuki, Masao; Tachi, Yukio

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.467 - 472, 2002/06

no abstracts in English

Journal Articles

Heat transfer characteristics of a steam reformer inserted metallic wire

Takeda, Tetsuaki

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.199 - 202, 2002/00

There are several methods for enhancement of heat transfer such as attaching various type fins on a channel surface of a heat exchanger tube and a steam reforming tube. The objective of this study is to clarify characteristics of heat transfer and pressure drop in the channel inserted metallic wire with high porosity. A heat transfer experiment was performed using a horizontal circular tube to obtain the heat transfer characteristics of the channel inserted copper wire. From the results obtained in this experiment, it seems to be probable that an enhancement of heat transfer method using metallic wire inserts is further improved under the high temperature conditions in efficiency as compared with the other methods.

Journal Articles

Design study on Reduced-Moderation Water Reactor (RMWR)

Okubo, Tsutomu; Iwamura, Takamichi; Yamamoto, Kazuhiko*; Okada, Hiroyuki*

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.571 - 574, 2002/00

Based on the experienced light water reactor technology, conceptual design studies on advanced water-cooled reactors have been performed. They are named “Reduced-Moderation Water Reactor" (RMWR) with the high conversion ratio more than 1.0 and the negative void reactivity coefficients. Several concepts have been successfully established for them based on the neutronics calculations. Based on these concepts, detailed investigations on such as plutonium multiple recycling and control rod planning have been performed as well as improvement on core performances. Through these detailed core design investigation, the feasibility of those designs has been confirmed step by step.

Journal Articles

Development of an advanced reprocessing process of spent nuclear fuel

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.483 - 488, 2002/00

no abstracts in English

Journal Articles

Design of power conversion system of Gas Turbine High Temperature Reactor (GTGTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Katanishi, Shoji; Kosugiyama, Shinichi; Shiozawa, Shusaku

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.189 - 192, 2002/00

no abstracts in English

Journal Articles

Safety design philosophy on the Gas Turbine High Temperature Reactor 300 (GTHTR300)

Katanishi, Shoji; Kunitomi, Kazuhiko; Takada, Shoji; Nakata, Tetsuo; Takizuka, Takakazu; Shiozawa, Shusaku

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.185 - 188, 2002/00

no abstracts in English

Journal Articles

Design study on Gas Turbine High Temperature Reactor (GTHTR300) in FY2001

Kunitomi, Kazuhiko; Katanishi, Shoji; Takada, Shoji; Takizuka, Takakazu; Yan, X.; Nakata, Tetsuo; Takei, Masanobu; Kosugiyama, Shinichi; Shiozawa, Shusaku

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.181 - 184, 2002/00

no abstracts in English

Journal Articles

Source term analysis for severe accident conditions of a nuclear power plant

Ishikawa, Jun; Shintani, Kiyonori; Takagi, Seiji; Muramatsu, Ken

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.203 - 208, 2002/00

no abstracts in English

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