Fuel irradiation research of Japan at Halden reactor; Achievement of cooperative researches between JAERI and several organizations in the period from 2000 to 2002 (Joint research)

Committee of the Halden Joint Research Programme

JAERI-Tech 2004-023, 38 Pages, 2004/03

JAERI-Tech-2004-023.pdf:1.85MB

JAERI has performed cooperative researches with several Japanese organizations utilizing the Halden Boiling Heavy Water Reactor(HBWR) which is located at Halden in Norway. These researches are carried out based on the contracts of the cooperative researches, which are revised every three years, in accordance with the renewal of the participation of JAERI to the OECD Halden Reactor Project. This report summarizes the objectives, contents and the outlines of the achievements of the cooperative researches during the three years from 2000 January to 2002 December. During the period, seven cooperative researches had been carried out. Two of them had been completed and other five researches have been continued to the next three years period. Most of them are irradiation test researches of advanced fuel and cladding in order to prepare the higher burnup utilization and introduction of LWR fuel and MOX fuel in LWRs of Japan.

Enlarged HPG Meeting

Nakamura, Jinichi

Kaku Nenryo, (31), p.31_21 - 31_22, 1999/06

no abstracts in English

Thermal diffusivity measurement of high burnup UO pellet

Nakamura, Jinichi; Uchida, Masaaki; Uetsuka, Hiroshi; Kodaira, Tsuneo; Yamahara, Takeshi;

Proc. of Int. Topical Meeting on LWR Fuel Performance, 0, p.499 - 506, 1997/03

no abstracts in English

Post-irradiation examination of high burnup HBWR fuel rods at JAERI

Nakamura, Jinichi; Uetsuka, Hiroshi; Kono, Nobuaki; ; ; Furuta, Teruo

HPR-345 (Vol. II), 0, 13 Pages, 1995/00

no abstracts in English

Experimental plan on irradiated LWR fuels at JAERI

Uetsuka, Hiroshi; Nakamura, Jinichi; Nagase, Fumihisa; Uchida, Masaaki; Furuta, Teruo

Fuel Performance Experiment and Analysis and Computerised Man-Machine Communication, p.1 - 11, 1990/09

no abstracts in English

Fuel densification and swelling; Relationship between burn-up induced asial and radial fuel dimensional changes

Nucl.Eng.Des., 96, p.11 - 20, 1986/00

https://doi.org/10.1016/0029-5493(86)90158-5

no abstracts in English

IN-CORE BURNOUT FAILURE OF PWR TYPE FUEL ROD AND ITS BEHAVIOURAL ANALYSIS BY USING EQUIPPED INSTRUMENTATIONS

JAERI-M 84-009, 45 Pages, 1984/02

JAERI-M-84-009.pdf:1.95MB

no abstracts in English

Preliminary Analysis of Data for IFA-508(I),No2; Diameter Deformation of Fuel Rod: Irradiation Period:From June to July 1977 Attained Burnups:70MWd/tUO

JAERI-M 7711, 52 Pages, 1978/06

JAERI-M-7711.pdf:1.79MB

no abstracts in English

Preliminary Analysis of Data for IFA-508(I),No1; Elongation and Centre Temperature of Fuel, Irradiation Period : From June to August,1977,Burnups:1600 MWd/tUO

;

JAERI-M 7520, 29 Pages, 1978/02

JAERI-M-7520.pdf:0.76MB

no abstracts in English