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.

Pu Vector Sensitivity Study for a Pu Burning Fast Reactor Part II:Rod Worth Assessment and Design Optimization

Hunter

PNC TN9410 97-057, 106 Pages, 1997/05

PNC-TN9410-97-057.pdf:2.99MB

This study was based on a 'pancake' type fast reactor core design of 600 MW(e), which had been optimized for Pu burning with a feed Pu vector appropriate to once-through irradiation of MOX fuel in a PWR. The purpose of the study was to investigate the effects of varying the Pu vector, examining various methods of offsetting the effects of such a change, and finally to produce fuel cycles optimized for the different qualities of Pu vector within the same basic design. In addition to the reference (once-through) Pu vector, two extreme Pu vectors were examined: high quality Pu from military stockpiles; low quality Pu corresponding to the equilibrium point of multiple recycling in a Pu burning fast reactor. Variations in Pu quality were overcome by changing the fuel inventory - replacing some of the fuel by diluent material, and altering the fuel pin size. Using absorber material (BC) as diluent improves the rod worth shutdown margin but degrades the Na void and Doppler safety parameters, a non-absorber diluent has the opposite effects, so a mix of the 2 material types was used to optimize the core characteristics. Of the non-absorber diluent materials examined, ZrH gave significantly better performance than all others; BC was the second choice for non-absorber diluent, because of its compatibility with BC absorber. It was not possible to accommodate the lower quality (multi-recycled) Pu vector without a significant increase in the fuel pin volume. It was not generally possible, especially with the increased fuel pin size, to achieve positive rod worth shutdown margins - this was overcome by increasing the number of control rods. For the higher quality Pu vectors to maintain ratings within limits, it was necessary to adopt hollow fuel pellets, or else to use the diluent material as an inert matrix in the fuel pellets. It proved possible to accommodate both extremes of Pu vector within a single basic design, maintaining ...

Conceptual study of test reactor for fuel irradiation/reactor performance research

Inabe, Teruo; ; ; Yonomoto, Taisuke; *; Akutsu, Cho; ; Iwamura, Takamichi; Okubo, Tsutomu; Osugi, Toshitaka; et al.

JAERI-M 93-106, 104 Pages, 1993/05

JAERI-M-93-106.pdf:2.77MB

no abstracts in English

Nuclear fuel and material irradiation test for the purpose of nuclear reactor development

Enerugi Rebyu, 11(10), p.11 - 15, 1991/09

no abstracts in English

Trial Irradiation in JMTR,Part2; FuelIrradiation

JAERI-M 5537, 299 Pages, 1974/03

JAERI-M-5537.pdf:13.39MB

no abstracts in English

Enhance safety measures to restart Joyo for fuel irradiation test, irradiation capability and role of Joyo

Yamamoto, Masaya; Itagaki, Wataru; Naito, Hiroyuki

no journal, , 

To enhance understandings and utilization of Joyo, give a lecture on safety design and safety evaluation of sodium cooled fast reactor's fuel, and irradiation capability of Joyo.