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Oral presentation

Development of the new type moderator vessel for the cold neutron source in the JRR-3, 1; Pressure test

Yoshinaga, Makio; Tamura, Itaru; Komeda, Masao; Yamamoto, Kazuyoshi; Sagawa, Hisashi

no journal, , 

no abstracts in English

Oral presentation

Cathodic protection of stainless steel in boiling nitric acid solutions

Uchiyama, Yohei; Kato, Chiaki; Ueno, Fumiyoshi; Yamamoto, Masahiro

no journal, , 

The cathodic protection applications of reprocessing plant made of stainless steel in boiling nitric acid solutions was studied. In this study, 304ULC stainless steels in 3N HNO$$_{3}$$ solutions was investigated, Saturated Silver chloride Electrode (SSE) was used as reference electrode. Results of potentiostatic corrosion test was that corrosion rates shows an exponential function increase with rises of potential in transpassive state regions and finded possibility of the cathodic protection applications. Corrosion rates with cathodic protection was about one fortieth of without cathodic protection in boiling nitric acid solutions added 10 g/L vanadium ions (imitation solutions of reprocessing).

Oral presentation

Unofficial duty handing over and authority cognition; Cause analysis of JCO criticality accident

Tanabe, Fumiya

no journal, , 

One of the major causes of JCO criticality accident is that the change of procedure of homogenization of product solution from the storage tank into the precipitation tank was permitted by the manager of planning group. Unofficial duty handing over by the retiring manager of the special crew (SC) influenced significantly the foreman's cognition that the SC foreman had the role and authority to ask the permission.

Oral presentation

Rewetting velocity model during post-BT for anticipated operational occurence of BWR

Shibamoto, Yasuteru; Maruyama, Yu; Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

A Study to improve an accuracy of multi-group libraries for reactor calculations, 2

Chiba, Go; Okumura, Keisuke

no journal, , 

In order to improve accuracy of effective cross section calculations for MA and FP nuclides, we propose a new method in which a detail energy spectrum of neutron flux, which is depressed by the uranium-238 resonances, is utilized in the generation process of multi-group libraries. We produced a 107-group multi-group library with the proposed method, and utilized it for a burn-up calculation of LWR pincells. We found that this library predicts the number densities of MA and FP nuclides after burn-up very well.

Oral presentation

Development of safety review method for hot laboratories, 1; Safety review method for hot laboratories

Mizukoshi, Yasutaka; Fujishima, Tadatsune; Sakamoto, Naoki; Amagai, Tomio; Omori, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Development of safety review method for hot laboratories, 2; Operation experiences and safety review of hot laboratories

Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Amagai, Tomio; Omori, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Electro-deposition behavior of TRU with liquid Cd cathode

Kofuji, Hirohide; Fukushima, Mineo; Myochin, Munetaka; Kormilitzyn, M.*; Terai, Takayuki*

no journal, , 

In the metal electrorefining reprocessing method, transuranic elements (TRU) are recovered simultaneously with the liquid cadmium cathode (LCC) and are decontaminated from the fission products dissolving in the melt. Lab-scale experiments were carried out to evaluate the performance of TRU recoverly with LCC using U, Pu and minor actinides (MA), and it was confirmed that TRU could be recoverd simultaneously with LCC by electrode position.

Oral presentation

Development of safety review method for hot laboratories, 3; Remote maintenance techniques for hot laboratories

Sakamoto, Naoki; Yoshikawa, Katsunori; Kushida, Naoya; Nagamine, Tsuyoshi; Sukegawa, Kiyoshi*

no journal, , 

no abstracts in English

Oral presentation

Plasma arc cutting test using the JPDR dismantling waste, 2; Particle size distribution and dispersion mechanism of the radioactive aerosols

Takamura, Atsushi; Shimada, Taro; Oshima, Soichiro; Uno, Yuichi; Gunji, Soichi*; Ito, Takeshi; Sukegawa, Takenori; Tanaka, Tadao; Nakayama, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Development of hydride neutron absorber for fast reactor; Sodium compatibility test of hafnium hydride, 2

Hirakawa, Yasushi; Konashi, Kenji*

no journal, , 

no abstracts in English

Oral presentation

Plasma arc cutting test using the JPDR dismantling waste, 1; Evaluation of dispersion rate of the radioactive aerosols

Shimada, Taro; Takamura, Atsushi; Oshima, Soichiro; Uno, Yuichi; Gunji, Soichi*; Ito, Takeshi; Sukegawa, Takenori; Tanaka, Tadao; Nakayama, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Analytical survey of an irradiation condition in JRR-3 to achieve uniform profile in 12 inch silicon

Komeda, Masao; Yamamoto, Kazuyoshi; Magome, Hirokatsu; Isshiki, Masahiko*; Sagawa, Hisashi

no journal, , 

no abstracts in English

Oral presentation

Study on effectivity of the environmental monitoring data for judging final site status after decommissioning

Sukegawa, Takenori; Shimada, Taro; Uno, Yuichi; Oshima, Soichiro; Ito, Takeshi; Takamura, Atsushi; Tanaka, Tadao; Nakayama, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Engineering scale demonstration test of centrifugal contactor system, 7; Examination on operating conditions for solvent flushout

Arai, Yoichi; Ogino, Hideki; Onose, Tsutomu*; Kase, Takeshi; Nakajima, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Development of design technology on carryover from free-surface in the upper plenum of natural-circulation type BWRs, 5; Measurement of droplet quality based on isenthalpic change

Tamai, Hidesada; Nagayoshi, Takuji; Katono, Kenichi; Ito, Takashi; Takase, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Neutron irradiation techniques to enhance therapeutic dose of neutron capture therapy at JRR-4, 1; Improvement of epithermal neutron beam with removal of graphite in medical neutron beam facility

Nakamura, Takemi; Kumada, Hiroaki; Yamamoto, Kazuyoshi; Kishi, Toshiaki; Wada, Shigeru

no journal, , 

no abstracts in English

Oral presentation

Bonding strength of a dissimilar metal joint between reduced activation ferritic steel and beryllium

Ogiwara, Hiroyuki*; Ando, Masami; Tanigawa, Hiroyasu; Enoeda, Mikio; Akiba, Masato; Hirose, Takanori

no journal, , 

no abstracts in English

Oral presentation

Long-term treatment test of steam reformer for waste oraganic solvent containing uranium

Koyama, Hayato; Sone, Tomoyuki; Sasaki, Toshiki; Yamashita, Toshiyuki

no journal, , 

no abstracts in English

Oral presentation

Neutron irradiation techniques for neutron capture therapy at JRR-4, 2; Development of thermal neutron filter and application of a new beam mode to increase neutron intensity

Kumada, Hiroaki; Nakamura, Takemi; Sakurai, Yoshinori*; Maruhashi, Akira*; Ono, Koji*; Matsumura, Akira*

no journal, , 

no abstracts in English

266 (Records 1-20 displayed on this page)