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JAEA Reports

Study of the quality of vipac oxide fuel obtained by pyro-processing

Kakehi, Isao;

JNC TN9400 2000-054, 84 Pages, 2000/04

JNC-TN9400-2000-054.pdf:7.15MB

This report describes accomplishment of the study on the quality of vipac (vibro-packed) oxide fuel obtained by pyrochemical processing (molten salt electrolytic processing). This study is intended to contribute to the design study of the pyro-reprocessing-vipac fuel recycling system of oxide fuel. In this study, vibro-packing experiment has been conducted using granular U0$$_{2}$$ obtained by molten salt electrolytic processing (cold experiment). The oxide pyro process developed by Research lnstitute of Atomic Reactors (RIAR) is the method in which the sintered oxide is electrically deposited on the cathode at approximately 600$$^{circ}$$C. 0xide granules for vipac fuel are obtained by crushing the oxide deposited on the cathode. This process is also developed as recycle process because it is capable of FP separation. Also in Japan, this process is studied as one of the new FBR fuel recycling systems. ln this study, we made an effort to clarify the mechanisms of vibro-packing of the electrically obtained granules, which influence on the effective parameters of vibro-packing density and fuel particles size distribution in the fuel cladding in case of non-sphere particles of the granules. As a result of the study, smear density of 75% and almost uniform distribution of U0$$_{2}$$ particles have been taken in the experiment, and much knowledge for the improvement of the vibro-packing quality has been found. And the possibility of the smear density over 80% and the uniform distribution of U0$$_{2}$$ particles has been suggested in this study.

Journal Articles

Helium release from neutron-irradiated Li$$_{2}$$O sintered pellets

Tanifuji, Takaaki; Yamaki, Daiju; Noda, Kenji

Fusion Engineering and Design, 39-40, p.723 - 729, 1998/00

no abstracts in English

JAEA Reports

None

PNC TJ1635 97-001, 3 Pages, 1997/03

PNC-TJ1635-97-001.pdf:7.49MB

no abstracts in English

JAEA Reports

Development of off-line load sensor; Characterization of sintered-metal load gauge element (2)

; ; ; ; ; Kano, Shigeki

PNC TN9410 94-351, 97 Pages, 1994/09

PNC-TN9410-94-351.pdf:3.41MB

Subsequent to the previuos testing (PNC SN9410 90-082, June 1990), characterization has been made on the sintered-metal load gauge element. The sintered-metal load gauge element was developed for use in off-line load measurement in the reactor environment. The testing conducted is as follows : (1)Characterization test phase II (a)Compression Tests for Initial Adjustment (b)Geometrical Parameter Compression Tests (c)Inclined Compression Tests (d)Creep Tests at Elevated Temperature (2)Characterization test phase III (For application in the reactor environment, the sintered-metal was covered with thin plates.) (a)Compression Tests for Initial Adjustment (b)Compression Tests at Elevated Temperatures (c)Inclined Compression Tests at Elevated Temperatures The results have shown that the sintered-metal load gauge element is applicable in the reactor environment. In association with the characterization tests, method for practical applications in JOYO and extended application have also been investigated.

Journal Articles

Fabrication of lithium ceramic pellets, rings, and single crystals for irradiation in BEATRIX-II

O.D.Slagle*; Noda, Kenji;

Adv.Ceram., 27, p.77 - 93, 1990/00

no abstracts in English

Journal Articles

Tritium release from neutron-irradiated Li$$_{2}$$O; Constant rate heating measurements

Tanifuji, Takaaki; ; ; *

Journal of Nuclear Materials, 95(1-2), p.108 - 118, 1980/00

 Times Cited Count:30 Percentile:91.36(Materials Science, Multidisciplinary)

no abstracts in English

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