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Journal Articles

Re-evaluation of nuclear data of fission product nuclides for JENDL-3.2

Kawai, Masayoshi*; Nakagawa, Tsuneo; Watanabe, Takashi*; Nakajima, Yutaka*; Zukeran, Atsushi*; Matsunobu, Hiroyuki*; Sugi, Teruo*; Chiba, Satoshi

Journal of Nuclear Science and Technology, 38(4), p.261 - 269, 2001/04

no abstracts in English

Journal Articles

Conversion of JRR-4 fuel to LEU

Watanabe, Shukichi; Nakajima, Teruo; Kaieda, Keisuke

JAERI-Conf 99-006, p.119 - 124, 1999/08

no abstracts in English

Journal Articles

Modification of JRR-4; Remodeling of reactor building

; ; ; Nakajima, Teruo; Akutsu, Yoichi; ; Naruse, Hideo

UTNL-R-0378, p.6.1 - 6.9, 1999/00

no abstracts in English

Journal Articles

Status of JRR-4 modification works

Nakajima, Teruo; Bamba, Masao; ; ; Horiguchi, Yoji; Kaieda, Keisuke

Proc. of 6th Meeting of the Int. Group on Research Reactors, p.51 - 56, 1998/00

no abstracts in English

Journal Articles

A New medical irradiation facility at JRR-4

; Nakajima, Teruo; ; ; ;

Advances in Neutron Capture Therapy, 1, p.326 - 330, 1997/00

no abstracts in English

JAEA Reports

Basic experiments of reactor physics using the research reactor JRR-4 and NSRR

Obara, Toru*; Horiki, Oichiro*; Nakajima, Teruo; Watanabe, Shukichi; Ishijima, Kiyomi; Katanishi, Shoji

JAERI-Review 95-010, 39 Pages, 1995/06

JAERI-Review-95-010.pdf:1.14MB

no abstracts in English

Journal Articles

Comparison of JRR-4 core neutronic performance between silicide fuel and TRIGA fuel

Nakano, Yoshihiro; Ichikawa, Hiroki; Nakajima, Teruo

Proc. of the 16th Int. Meeting on Reduced Enrichment for Research and Test Reactors, 0, p.313 - 320, 1994/03

no abstracts in English

Journal Articles

JENDL-3 fission product nuclear data library

Kawai, Masayoshi*; Iijima, Shungo*; Nakagawa, Tsuneo; Nakajima, Yutaka; Sugi, Teruo; Watanabe, Takashi*; Matsunobu, Hiroyuki*; ;

Journal of Nuclear Science and Technology, 29(3), p.195 - 213, 1992/03

no abstracts in English

Journal Articles

JENDL-3 FP nuclear data library

Nakagawa, Tsuneo; Kawai, Masayoshi*; Iijima, Shungo*; Matsunobu, Hiroyuki*; Watanabe, Takashi*; Nakajima, Yutaka; Sugi, Teruo; ; ; ; et al.

Nuclear Data for Science and Technology, p.939 - 941, 1992/00

no abstracts in English

Oral presentation

Development of advanced vitrification melter; Examination on the discharge of particulate in vitrified waste

Morikawa, Yo; Yamashita, Teruo; Nakajima, Masayoshi; Nakazaki, Katsutoshi; Sasage, Kenichi

no journal, , 

no abstracts in English

Oral presentation

Development of advanced vitrification melter, 15; Evaluation of temperature of wall by the small scale melter

Yamashita, Teruo; Masaki, Toshio; Nakajima, Masayoshi; Nakazaki, Katsutoshi; Toyoshima, Mikihiro

no journal, , 

no abstracts in English

Oral presentation

Development of long-life vitrification melter, 14; Evaluation of temperature distribution by the small scale test melter

Yamashita, Teruo; Masaki, Toshio; Nakajima, Masayoshi; Shiotsuki, Masao; Kojima, Keizo; Toyoshima, Mikihiro; Matsumoto, Shiro*

no journal, , 

no abstracts in English

Oral presentation

Development of long-life vitrification melter, 12; Examination on the discharge of particulate in vitrified waste

Morikawa, Yo; Miyauchi, Atsushi; Nakajima, Masayoshi; Toyoshima, Mikihiro; Yamashita, Teruo; Shiotsuki, Masao; Matsumoto, Shiro*

no journal, , 

no abstracts in English

Oral presentation

Development of simulation system for vitrification melter, 2; Evaluation on physical behavior of the TVF melter during ordinary operation

Miura, Akihiko; Nakajima, Masayoshi; Yamashita, Teruo; Sakai, Takaaki; Shiotsuki, Masao; Sato, Akihiro*; Kawahara, Hitoshi*

no journal, , 

no abstracts in English

Oral presentation

Development of simulation system for vitrification melter, 1; Design and models newly applied in the simulation system

Nakajima, Masayoshi; Miura, Akihiko; Yamashita, Teruo; Sakai, Takaaki; Shiotsuki, Masao; Kawahara, Hitoshi*; Sato, Akihiro*

no journal, , 

no abstracts in English

Oral presentation

Development of long-life vitrification melter, 11; Influence of suspended particle on viscosity of molten glass

Sasage, Kenichi; Nakajima, Masayoshi; Yamashita, Teruo; Shiotsuki, Masao; Matsumoto, Shiro*

no journal, , 

no abstracts in English

Oral presentation

Study on Noble Metals sedimentation and viscosity of molten glass

Miyauchi, Atsushi; Nakajima, Masayoshi; Morikawa, Yo; Masaki, Toshio; Kobayashi, Hidekazu; Yamashita, Teruo; Komamine, Satoshi*; Ochi, Eiji*

no journal, , 

no abstracts in English

Oral presentation

Study on the sedimentation behavior of the noble metal particles in molten borosilicate glass

Oyama, Koichi; Morikawa, Yo; Miyauchi, Atsushi; Nakajima, Masayoshi; Yamashita, Teruo; Komamine, Satoshi*; Ochi, Eiji*

no journal, , 

no abstracts in English

Oral presentation

Investigation of coagulated glass included noble metal compounds by Raman spectroscopy

Nagai, Takayuki; Oyama, Koichi; Kobayashi, Hidekazu; Morikawa, Yo; Yokozawa, Takuma; Nakajima, Masayoshi; Yamashita, Teruo; Amamoto, Ippei

no journal, , 

no abstracts in English

Oral presentation

Sedimentation behavior of noble metal particles in simulated high-level waste borosilicate glasses

Nakajima, Masayoshi; Oyama, Koichi; Morikawa, Yo; Miyauchi, Atsushi; Yamashita, Teruo; Komamine, Satoshi*; Ochi, Eiji*

no journal, , 

Noble metal elements (NME) contained in high level liquid waste (HLLW) are distributed in a vitrification melter. Some part of them forms sediment which causes negative effects to steady operation of the melter. The formation process and characteristics of the sediment is useful information for considering methods of removing or discharging them. Thus the sedimentation observation was carried out by using simulated glass. Samples with 1.1wt% of initial NME concentration held at 1100$$^{circ}$$C indicated zone settling, and the settling rate of interface is constant; 2.4 mm/h. This sedimentation behavior is the type of rapid settling. Following the rapid settling, the settling rate goes slower gradually, this is the type of compressive settling. The samples whose initial NME concentrations are 3.0wt% and 6.1wt% showed compression settling form the beginning. From the settling curve of interface, the maximum concentration of NME in sediment was estimated as around 23-26wt%. This value can specify the properties of sediment to be removed, Also, growth of NME particles was observed by holding at 1100$$^{circ}$$C for up to 2880 hours.

27 (Records 1-20 displayed on this page)