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Morimoto, Kyoichi; Shibata, Atsuhiro; Shigetome, Yoshiaki
JNC TN8200 2001-006, 19 Pages, 2001/12
JNC-TN8200-2001-006.pdf:0.92MB
Global2001 (International Conference: "Back-End of the Fuel Cycle: From Research to Solutions ") was held for six days from September 9 to September 14 in Paris in France. In this year, there were about 420 participants from each country and about 70 people participated from Japan. This conference consisted of the reactor and fuel cycle field, the reprocessing field, the disposal field, and the non-proliferation field, etc. The main topics of this conference were the back end of the nuclear fuel cycle, the management of long-lived nuclide, the advanced concept of reactor and fuels. Advanced fuel recycle technology division reported about the feasibility study on commercialized FR cycle systems, the nuclear fuel and the reprocessing process in the oral session and poster session. Each report was audited and information was collected. It is possible to refer to information on Global2001 by the following homepages. http://www.cea.fr/conferences/global2001 /index.him*
*
JNC TN9440 2000-008, 79 Pages, 2000/08
JNC-TN9440-2000-008.pdf:2.33MB
This report summarizes the operating and irradiatlon data of the experimental reactor "JOYO" 35th cycle. Irradiation tests in the 35th cycle are as follows: (1)C-type irradiation rig (C4F) (a)High burnup performance test of advanced austenitic stainless steel cladding fuel pins (in collaboration with France) (2)C-type irradiation rig (C6D) (a)Large diameter fuel pins irradiation tests (3)Core Materials Irradiation Rig (CMIR-5) (a)Cladding tube materials irradiation tests for "MONJU" (4)Structure Materials Irradiation Rigs (SMIR) (a)Decision of material design base standard of structure materials for prototype reactor and large scale reactor (5)Upper core structure irradiation Plug Rig (UPR-1-5) (a)Upper core neutron spectrum effect and accelerated irradiation effect (6)SurVeillance un-instrument Irradiation Rig (SVIR) (a)Confimation of surveillance irradiation condition for "JOYO" (b)Material irradiation tests (based on a contract with universities) The maximum burnup driver assembly "PFD253" reached 67,600 MWd/t (pin average).
Ono, Takahiro*; Higuchi, Takanao*; Kazama, T.*; Hashimoto, T.*; Seito, Y.*; Hattori, Tomomi*; Kanamori, Miwa*
JNC TJ1420 2000-005, 257 Pages, 2000/03
JNC-TJ1420-2000-005.pdf:9.53MB
None
Otagaki, Takao*
JNC TJ1420 2000-004, 159 Pages, 2000/03
JNC-TJ1420-2000-004.pdf:4.82MB
no abstracts in English
Savage, D.*; Arthur, R. C,*; Sasamoto, Hiroshi; Shibata, Masahiro; Yui, Mikazu
JNC TN8400 2000-003, 56 Pages, 2000/01
JNC-TN8400-2000-003.pdf:1.96MB
Geochemical as well as socio-economic issues associated with the selection of potential sites to host a high-level nuclear waste repository have received considerable attention in repository programs in Europe (Belgium, Finland, France, Germany, Spain, Sweden, Switzerland and the U.K.) and North America (Canada and the United States), The objective of the present study is to summarize this international experience with particular emphasis on geochemical properties that factor into the adopted site-selection strategies. Results indicate that the geochemical properties of a site play a subordinate role, at best, to other geotechnical properties in the international site-selection approaches. In countries where geochemical properties are acknowledged in the site-selection approach, requirements are stated qualitatively and tend to focus on associated impacts on the stability of the engineered barrier system and on radionuclide transport. Site geochemical properties that are likely to control the lomg-term stability of geochemical conditions and radionuclide migration behavior are unspecified, however. This non-prescriptive approach may be reasonable for purposes of screeing among potential sites, but a better understanding of site properties that are most important in controlling the long-term geochemical evolution of the site over a range of possible scenarios would enable the potential sites to be ranked in terms of their suitability to host a repository.
Shigetome, Yoshiaki; ; ; Miura, Akihiko; Sato, Yoshihiko; Koyama, Tomozo
JNC TN8200 99-001, 128 Pages, 1999/07
None
Nemoto, K.*; *; Higuchi, Takanao*; Endo, H.*; Ono, Takahiro*; *; *
PNC TJ1250 98-002, 321 Pages, 1998/02
None
Yamato, Aiji; Sasaki, Noriaki; ; Miyahara, Kaname
PNC TN1100 94-002, 85 Pages, 1993/11
Nuclear energy is the second largest source of electric power in the United States. Tdate, nuclear power plants produced over twenty percent of the nation's electricity. Aof August 1991, there were 112 nuclear power reactors in the United States, and two mo were being built. By the year 2000, approximately 40,000 metric tons of nuclear wasteill be in temporary storage at reactor sites throughout the coutry. That amount is twi the amount that currently exists. In order to handle such waste, as well as the addedolume to be produced after the year 2000, the U. S. Department of Energt (DOE) is in t process of developing the waste management system that was authorized by the U. S Coness in 1987. The authorized system is illustrated in Figure 1. To summarize, spent nucar fuel from commercial power reactors will be accepted by the DOE at the reactor siteand transported to a monitored retrievable storage (MRS) facility for temporary storagand preparation for permanent disposal in a gelogic rep