Hostname: page-component-848d4c4894-75dct Total loading time: 0 Render date: 2024-05-01T06:12:03.229Z Has data issue: false hasContentIssue false
  • English
  • Français

Key Aspects of the H12 Safety Case

Published online by Cambridge University Press:  21 March 2011

Hiroyuki Umeki
Hiroyuki Umeki*
Affiliation:
Japan Nuclear Cycle Development Institute (JNC), 1-1-2 Marunouchi Chiyoda-ku, Tokyo 100-8245, Japan
Get access

Abstract

In Japan, as outlined in the overall high-level radioactive waste (HLW) management program defined by the Japanese Atomic Energy Commission (AEC, 1994), HLW from reprocessing of spent nuclear fuel will be immobilized in a glass matrix and stored for a period of 30 to 50 years to allow cooling. It will then be disposed of in a deep geological formation. Pursuant to the overall HLW management program, an organization with responsibility for implementing HLW disposal will be established around the year 2000. This will be followed by site selection and characterization, demonstration of disposal technology, establishment of the necessary legal infrastructure, relevant licensing applications and repository construction, with the objective of starting repository operation by the 2030s and no later than the mid 2040s.

The HLW disposal program is currently in the research and development (R&D) phase and the Japan Nuclear Cycle Development Institute (JNC) has been assigned as the leading organization responsible for R&D activities. The aim of the R&D activities at the current stage is to provide a scientific and technical basis for the geological disposal of HLW in Japan and to promote understanding of the safety concept not only in the scientific and technical community but also by the general public. One of the features of the R&D program is that its progress is documented at appropriate intervals, with a view to clearly determining the level of achievement of the program and to promote understanding and acceptance of the geological disposal strategy by the general public. As a major milestone, the Power Reactor and Nuclear Fuel Development Corporation (PNC, now JNC) submitted a first progress report, referred to as H3 (PNC, 1992), in September 1992.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 701
Copyright
Copyright © Materials Research Society 2001

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1.AEC (1994): Long-Term Program for Research, Development and Utilization of Nuclear Energy.Google Scholar
2.AEC(1997): Guidelines on Research and Development Relating to Geological Disposal of High-level Radioactive Waste in Japan.Google Scholar
3. Berner, U. (1995): KRISTALLIN-I: Estimates of Solubility Limits for Safety Relevant Radionuclides, PSI Bericht Nr. 95-07.Google Scholar
4.BIOMASS (1999): Long-Term Releases from Solid Waste Disposal Facilities: The Reference Biosphere Concept, BIOMASS Theme 1 Working Document: BIOMASS/T1/WD01, IAEA, Vienna.Google Scholar
5. Bruno, J., Cera, E., Pablo, J., Duro, L., Jordana, S. and Savage, D. (1997):Determination of Radionuclide Solubility Limits to be used in SR 97; Uncertainties Associated to Calculated Solubilities, SKB Technical Report 97-33.Google Scholar
6. Ijiri, Y., Sawada, A., Webb, E.K., Watari, S., Hatanaka, K., Uchida, M., Ishiguro, K., Umeki, H. and Dershowitz, W. S. (1998): Radionuclide Migration Analysis Using a Discrete Fracture Network Model, Proc. of the MRS 1998.Google Scholar
7.JNC (2000): H12 Project to Establish Technical Basis for HLW Disposal in Japan, Project Overview Report and three Supporting Reports, JNC TN1410 2000-001∼004.Google Scholar
8. Nagra (1994): Kristallin-I; Safety Assessment Report, Nagra Technical Report, NTB 93-22, Nagra, Wettingen, Switzerland.Google Scholar
9. Neall, F.(ed.), Baertschi, P., McKinley, I.G., Smith, P.A., Sumerling, T.J. and Umeki, H. (1994) Kristallin-I, Results in Perspective, NTB 93-23, Nagra, Wettingen, Switzerland.Google Scholar
10. Oda, C., Yoshikawa, H. and Yui, M. (1996): Effects of Aging on the Solubility of Palladium, Mat. Soc. Symp. Proc., Vol.412, pp. 881–887.Google Scholar
11. Oda, C. and Amaya, T. (1998): Effects of Ligands on the Solubility of Tin, JNC TN8400 98-001.Google Scholar
12.OECD/NEA (1997): Safety Assessment of Radioactive Waste Repositories - Systematic Approaches to Scenario Development - An International Database of Features, Events and Processes. Draft Report (24/6/1997) of the NEA Working Group on Development of a Database of Features, Events and Processes Relevant to the Assessment of Post-Closure Safety of Radioactive Waste Repositories.Google Scholar
13.OECD/NEA and SKI (1994): GEOVAL'94 Validation Through Model Testing, Proceedings of an NEA/SKI Symposium Paris, France, 11-14 October 1994.Google Scholar
14.PNC (1992): Research and Development on Geological Disposal of High-level Radioactive Waste, First Progress Report - H3, PNC TN1410 93-059.Google Scholar
15. Shibutani, S. and Yui, M. (1998): Status of PNC-TDB Development for Performance Assessment, PNC Technical Review, No.105, pp.57–66 (in Japanese).Google Scholar
16. Takasu, A., Naito, M., Umeki, H. and Masuda, S. (2000): Application of Supplementary Safety Indicators for H12 Performance Assessment, MRS 2000, 24th International Symposium on the Scientific Basis for Nuclear Waste Management, August 27-31, 2000, Sydney, Australia.Google Scholar
17. Umeki, H. (1994): Comparison of Nagra Kristallin-I and PNC H3, Radioactive Waste Research Vol.1 No.1 pp.13–20 (in Japanese).Google Scholar
18. Yajima, T., Tobita, S. and Ueta, S. (1992): Solubility Measurement of Niobium in the system Nb-O-H under CO2-free Conditions, Proceedings of 1992 Fall Meeting of the Atomic Energy Society of Japan, F33, p.341 (in Japanese).Google Scholar
19. Yajima, T. (1994): Solubility Measurements of Uranium and Niobium, Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, Yayoi Kenkyuukai Report, UTNL-R 0331, pp.127–143 (in Japanese).Google Scholar
20. Vieno, T. and Nordman, H. (1999): Safety Assessment of Spent Fuel Disposal in Hastholmen, Kivetty, Olkiluoto and Romuvaara, TILA-99, POSIVA 99-07.Google Scholar
21. Yui, M., Azuma, J., and Shibata, M. (1999): JNC Thermodynamic Database for Performance Assessment of High-level Radioactive Waste Disposal System, JNC TN8400 99-070.Google Scholar