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Journal Articles

Research of uncertainty on long-term safety assessment for radioactive waste disposal

Takeda, Seiji; Kimura, Hideo

JAERI-Conf 2003-018, p.111 - 112, 2003/10

no abstracts in English

JAEA Reports

Discussion of uncertainties associated with parameters of biosphere model for safety assessment of geologieal disposal through sensitivity analysis

Kato, Tomoko; ; *;

JNC-TN8400 2001-014, 212 Pages, 2001/03

JNC-TN8400-2001-014.pdf:8.21MB

Reference Biospheres are regarded as tools which can be used for making reasonable estimates of radiological impacts for the purposes of safety assessment of geological disposal. Moreover, those are available for reducing the uncertainties based on future human environments and lifestyles. On the other hand, it is recognised that the parameter values have some uncertainties derived from experimental or sampling errors. It is possible to estimate the impacts of these uncertainties throughout the model by sensitivity analysis. Thus for this study, to evaluate the impact of the variation of migration conditions and exposure pathways, we changed some of migration and exposure parameters in turn, which were used in the compartment model where the geosphere-biosphere interface is a river in a plain.

JAEA Reports

Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

JAERI-Tech 2001-018, 88 Pages, 2001/03

JAERI-Tech-2001-018.pdf:5.66MB

no abstracts in English

JAEA Reports

Basic data for integrated assessment of nuclear fuel cycle system

Nomura, Yasushi; Tamaki, Hitoshi; Ito, Chihiro*; Saegusa, Toshiari*

JAERI-Data/Code 2001-012, 118 Pages, 2001/03

JAERI-Data-Code-2001-012.pdf:5.71MB

no abstracts in English

JAEA Reports

ICONE-8 participation and investigation report of dry process in Argonne National Laboratory (ANL), USA

; Washiya, Tadahiro;

JNC-TN8420 2001-009, 48 Pages, 2000/04

JNC-TN8420-2001-009.pdf:0.58MB

ICONE(International Conference on Nuclear Engineering) is an international conference on nuclear chemical engineering held among the United States, Japan and Europe, and ICONE8 (the 8th time of the conference) was held at Baltimore, USA on April 2 to 6, 2000. The authors of this paper reported the latest information on the reprocessing technology in the following session of the conference and audited the panel discussion and the technical report of the dry reprocessing technology etc. in the conference. (1)Investigation of Safety Evaluation Method and Application to Tokai Reprocessing Plant (TRP) in session of Track-5 "Non-reactor Safety and Reliability" (Nakamura) (2)Structural Improvement on the continuous rotary dissolver in session of Track-9 "Spent Nuclear Fuel and Waste Processing" (Washiya) (3)Development of Evaporators Made of Ti-5% Ta Alloy and Zr - Endurance Test By Mock-Up unit" in session of Track-2 "Aging and Modeling of Component Aging, Including corrosion of Metals and Welds.. passivation, and passive films" (Takata) At the conference, about 650 people participated from the United States, Japan, France, Canada and others, about700 research announcements, 7 keynote lecture and 8 panel discussion were done, flourishing with many participants. Moreover, as the conference was held in the year of 2000, the evaluation of this century and the direction of the next century of nuclear energy were discussed. After the conference, authors visited Argonne National Laboratory (ANL-E, ANL-W) and exchanged information concerning dry process with researchers of ANL-E and ANL-W, visiting ANL facilities. It was very significant to be able to acquire the information on the dry process developed in ANL and realize the device scale and the development environment, etc. and acquire technical information in detail which would not be able to obtain by engineering data, exchanging information with ANL engineers directly. It is suggested to be very valuable that the ...

JAEA Reports

Criticality safety evaluation in Tokai reprocessing plant

Shirai, Nobutoshi; ; ; Shirozu, Hidetomo; ; Hayashi, Shinichiro;

JNC-TN8410 2000-006, 116 Pages, 2000/04

JNC-TN8410-2000-006.pdf:2.77MB

Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 "Criticality safety of single unit" in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units.

Journal Articles

Thermal hydraulic characteristics during ingress of coolant and loss of vacuum events in fusion reactors

Takase, Kazuyuki; Kunugi, Tomoaki*; Seki, Yasushi; Akimoto, Hajime

Nuclear Fusion, 40(3Y), p.527 - 535, 2000/03

 Times Cited Count:8 Percentile:69.8(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Numerical prediction of two-phase flow behavior in a fusion reactor at an ingress-of-coolant event

Ose, Yasuo*; Takase, Kazuyuki; Akimoto, Hajime

Nippon Kikai Gakkai 2000-Nendo Nenji Taikai Koen Rombunshu, 1, p.609 - 610, 2000/00

no abstracts in English

JAEA Reports

None

JNC-TN8200 2000-001, 40 Pages, 1999/10

JNC-TN8200-2000-001.pdf:0.79MB

None

JAEA Reports

None

PNC-TN8020 91-003, 49 Pages, 1990/12

PNC-TN8020-91-003.pdf:1.18MB

no abstracts in English

JAEA Reports

Journal Articles

ICPR recommendations and safety evaluation by disposal of radioactive wastes; On the transuranic elements

Nippon Genshiryoku Gakkai-Shi, 25(10), p.795 - 800, 1983/00

 Percentile:100(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

15 (Records 1-15 displayed on this page)
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