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Ito, Haruhiko; Ide, Hiroshi; Yamaura, Takayuki; Tsuji, Tomoyuki
JAERI-Review 2004-001, 39 Pages, 2004/02
JAERI-Review-2004-001.pdf:2.02MB
no abstracts in English
Department of JMTR, Oarai; Department of Research Reactor, Tokai; Department of Hot Laboratories, Tokai
JAERI-Conf 2001-018, 109 Pages, 2002/01
JAERI-Conf-2001-018.pdf:13.67MB
The “Seminar on the Utilization of Neutron Irradiation" was held on March 9th 2000 in Tokai establishment as a part of activities of the “Program Committee for Neutron Irradiation". The topics presented in the seminar included the recent irradiation studies on the materials for the light water reactors, development of fusion reactor materials and materials used under high temperature, application of neutron activation and recent activities in the post irradiation examinations. This report contains the shortpapers and the copies of the OHPs presented at the seminar.
Kitajima, Toshio; Abe, Shinichi; Takahashi, Kiyoshi; Onuma, Yuichi; Watanabe, Hiroyuki; Okada, Yuji; Oyake, Noriyuki*
UTNL-R-0404, p.6_1 - 6_9, 2001/00
no abstracts in English
Fujiki, Kazuo
Nihon Genshiryoku Gakkai-Shi, 41(9), p.933 - 934, 1999/09
no abstracts in English
Tabata, Toshio; Komukai, Bunsaku; Nagao, Yoshiharu; Shimakawa, Satoshi; Koike, Sumio; Takeda, Takashi; Fujiki, Kazuo
JAERI-Tech 99-021, 68 Pages, 1999/03
no abstracts in English
; Department of JMTR
JAERI-Conf 98-007, 197 Pages, 1998/03
no abstracts in English
Hunter
PNC TN9410 98-015, 81 Pages, 1998/02
The study was carried out within the framework of the PNC-CEA collaboration agreement. Data were provided, by CEA, for an experimental loading of a start-up core in Super-Phenix. This data was used at PNC to produce core flux snapshot calculations. CEA undertook a comparison of the PNC results with the equivalent calculations carried out by CEA, and also with experimental measurements from SPX. The resu1ts revealed a systematic radial flux tilt between the calculations and the reactor measurements, with the PNC tilts only 
30-401 of those from CEA. CEA carried out an analysis of the component causes of the radial tilt. It was concluded that a major cause of radia1 tilt differences between the PNC and CEA calculations lay in the nuclear datasets used: JENDL-3.2 and CARNAVAL IV. For the final stage of the study, PNC undertook a sensitivity analysis, to examine the detailed differences between the two sets of nuclear data. The PNC flux calculations modelled SPX in both 2D (RZ) and 3D (hex-Z) geometries, using the diffusion programs CITATION and MOSES. The sensitivity analysis of the differences between the JENDL-3.2 and CARNAVAL IV nuclear datasets used the SAGEP calculational route. Both datasets were condensed to a single, non-standard, set of energy group boundaries. There were some incompatibilities in the cross-section formats of the two datasets. The sensitivity analysis showed that a relatively small number of nuclear data items contributed the bulk of the radial tilt difference between calculations with JENDL-3.2 and with CARNAVAL IV. A direct comparison between JENDL-3.2 and CARNAVAL IV data revealed the following. The Nu values showed little difference (<5|%). The only large fission cross-section differences were at low energy (<30% otherwise, with <10% typical). Although down-scattering reactions showed some large fractional differences, absolute differences were negligible compared with in-group scattering; for in-group scattering fractional ...
Miyasaka, Yasuhiko
Dekomisshoningu Giho, 0(14), p.24 - 33, 1996/08
no abstracts in English
Kanda, Keiji*; *; Isshiki, Masahiko; Baba, Osamu; Tsuruta, Harumichi
1996 Int. Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), 0, 8 Pages, 1996/00
no abstracts in English
Tsuchida, Noboru; Ooka, Norikazu; ;
ASRR-V: Proc., 5th Asian Symp. on Research Reactors, 1, p.123 - 130, 1996/00
no abstracts in English
JAERI-Research 95-026, 54 Pages, 1995/03
JAERI-Research-95-026.pdf:2.47MB
no abstracts in English
Miyasaka, Yasuhiko
Enerugi Rebyu, 15(9), p.11 - 15, 1995/00
no abstracts in English
Nakagiri, Toshio; ; Ohno, Shuji; ; *; Koyama, Shinichi; Shimoyama, Kazuhito
PNC TN9510 94-001, 246 Pages, 1994/05
None
Saito, Minoru; Yamamoto, Katsumune
Nihon Genshiryoku Gakkai-Shi, 36(4), p.321 - 322, 1994/00
no abstracts in English
Inabe, Teruo; ; ; Yonomoto, Taisuke; *; Akutsu, Cho; ; Iwamura, Takamichi; Okubo, Tsutomu; Osugi, Toshitaka; et al.
JAERI-M 93-106, 104 Pages, 1993/05
no abstracts in English
Takahashi, Hidetake; ; Hoshi, Michio; Funahashi, Satoru; Tsuruno, Akira; Kodaira, Tsuneo
Enerugi Rebyu, 11(10), p.4 - 30, 1991/09
no abstracts in English
; Takahashi, Takeshi
PNC TN8410 91-158, 19 Pages, 1991/04
Joule heated ceramic melter has been developed to vitrify high-level liquid wastes (HLLW) from reprocessing nuclear spent fuel at Power Reacter and Nuclear Fuel Development Corporation (PNC). Noble metal elements such as ruthenium, paladium and rhodium are contained as fission products in the HLLW. The operational chracteristics of Joule-heated ceramic melter were studied on the effects of these elements. Two small scale melters with sloped floor were fabricated and tested. The slope was 30
and 45 for each. The operational characteristics including electrode resistance, temperature profile etc. were monitored. The drain efficiency of noble metal elements from the melters during the glass drain operation were evaluated. After the test operation, the melters were cut after cooled with the glass left in the melting cavities, following the termination of the test operations. The sediments of the precipitations of the noble metal elements were evaluated from the sectional observation for the melter. The results from the studies were compared between 30 and 45 slopes and discussed. It was concluded that the 45 sloped floor was clearly effective to drain the noble metal elements and the structure of the 45 sloped floor melter was compatible with some amount of precipitates at the bottom.
Ishitsuka, Etsuo; Kawamura, Hiroshi; Sugai, Hiroyuki; Tanase, Masakazu;
JAERI-M 90-013, 37 Pages, 1990/02
no abstracts in English
; Hirata, Mitsuho
Multipurpose Research Reactors, p.331 - 338, 1988/00
no abstracts in English
