Second progress report on research and development for TRU waste disposal in Japan; Repository design, safety assessment and means of implementation in the generic phase

Japan Atomic Energy Agency; Federation of Electric Power Companies of Japan*

JAEA-Review 2007-010, 26 Pages, 2007/03

JAEA-Review-2007-010.pdf:4.0MB
JAEA-Review-2007-010-appendix(CD-ROM).zip:45.44MB

In order to promote the establishment of a regulatory framework and the implementation of TRU waste disposal, the Federation of Electric Power Companies of Japan (FEPC) and the Japan Nuclear Cycle Development Institute (now JAEA) collaborated and published a progress report in Japanese (hereafter TRU-2) in September 2005. The report here is an English version of TRU-2 and has been published to widely inform overseas researchers and engineers of the contents of TRU-2. In this report, the characteristics of TRU waste generated from the nuclear fuel cycle in Japan and its disposal concept are shown. The design of the TRU waste disposal facility was evaluated and safety assessments were carried out to show that safety could be validated by comparing with regulatory guidelines in overseas performance assessment reports. Alternative technologies were developed to deal with various geological environments and to improve safety margins in addition to evaluating other disposal concepts. Furthermore, optimisation through co-location disposal of TRU waste and high level radioactive waste was investigated, and an example layout of a co-location disposal concept was evaluated. Based on these evaluation results, future issues and outstanding items on research and development for TRU waste disposal are summarised.

Present and future studies for geological disposal of long half life radionuclides bearing low feverish radioactive waste

Kuroda, Shigeki*; Kamei, Gento

Genshiryoku Bakkuendo Kenkyu, 13(1), p.31 - 35, 2006/10

https://nuce.aesj.or.jp/jnuce/vol13/Jnuce-Vol13-1-p31-36.pdf

Long half-life low heat generating radioactive waste (TRU waste) containing higher amount of radionuclide is considered to be disposed into a geologic formation. As an optimized geologic disposal of the waste, a technical possibility of co-disposal with high-level radioactive waste is being studied. An assessment result shows that a co-disposal is possible in a Japanese representative geologic environment by setting these repositories at a certain distance apart because reciprocal influences can be avoided. Atomic Energy Commission of Japan deliberated on the result and judged that the co-disposal concept described in the 2nd progress TRU report has a technical possibility. On the other side, future studies are required from the view points of (1) more reliable assessment of co-disposal, (2) expansion of generic assessment basis, and (3) flexible correspondence for wide geologic environmental conditions. This article shows a current status of the investigations of TRU waste disposal including an overview of the disposal concept and concrete items for the future studies.

None

Ouchi, Masaru

JNC TY1400 2005-013, 590 Pages, 2005/09

JNC-TY1400-2005-013.pdf:49.28MB
JNC-TY1400-2005-013(errata).pdf:0.26MB

None

Strategy of research and development for TRU waste disposal

Kamei, Gento

no journal, , 

no abstracts in English

Influence of impurity of the stainless steel on intergranular corrosion in boiling nitric acid solutions

Kato, Chiaki; Kiuchi, Kiyoshi; Yamamoto, Masahiro

no journal, , 

It is known for the boiling nitric acid environment used in reprocessing facilities that stainless steel raises intergranular corrosion. In contrast, influence of the impurity element to separate in a grain boundary is pointed out. As a result of it reduced an impurity element this time, and having examined grain boundary corrosiveness of the SUS310 steel which I made by two kinds of process-resistant, it became clear that influence of the trace element was remarkable. The stainless steel which reduced such a trace element had high grain boundary corrosiveness-resistant, and the thing that was promising as high corrosion resistance material in the whole boiling nitric acid became clear.