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o Negro, ArgentinaCocco, R. G.*; Ishida, V.*; Tsuchiya, Kunihiko; Dorn, C. K.*
JAEA-Review 2014-012, 122 Pages, 2014/03
JAEA-Review-2014-012.pdf:15.65MB
This report summarizes the documents presented in the 8th Specialist Meeting on Recycling of Irradiated Beryllium, which held on October 28, 2013, in Bariloche, Ro Negro, Argentina, hosted by INVAP and CNEA (Comision Nacional de Energia Atomica). The objective of the meeting is to exchange the information of current status and future plan for beryllium study in the Research/Testing reactors. In this meeting, presentations on current status and future plan for beryllium study were carried out for the Research/Testing reactor fields from U.S.A., Korea, Argentina and Japan. Evaluation results of beryllium materials were discussed based on new data such as swelling, deformation, gas release and so on of irradiated beryllium. The subject of the used beryllium recycling was also discussed for the enforcement of demonstration recycling tests.
Dorn, C. K.*; Tsuchiya, Kunihiko; Takemoto, Noriyuki; Ito, Masayasu; Hori, Junichi*; Chekushina, L.*; Hatano, Yuji*; Chakrov, P.*; Kawamura, Hiroshi
Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 9 Pages, 2013/10
no abstracts in English
Tsuchiya, Kunihiko; Ito, Masayasu; Kitagishi, Shigeru; Endo, Yasuichi; Saito, Takashi; Hanawa, Yoshio; Dorn, C. K.*
JAEA-Conf 2012-002, p.111 - 114, 2012/12
no abstracts in English
Dorn, C. K.*; Tsuchiya, Kunihiko; Hatano, Yuji*; Chakrov, P.*; Kodama, Mitsuo*; Kawamura, Hiroshi
Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 9 Pages, 2012/10
The JMTR has used beryllium reflector since it began operation in 1968. Beryllium has been used as the reflector element material in the reactor, specifically S-200F structural grade beryllium in JMTR. As a part of the reactor upgrade, the Japan Atomic Energy Agency (JAEA) has carried out the cooperation experiments to extend the operating lifetime of the beryllium reflector elements. Thus, three kinds of beryllium metals such as S-200F, S-65H and I-220H were selected at the viewpoints of production methods, impurities and grain size of beryllium starting powders, mechanical properties. Now, data of the material properties and interaction between pure water and these beryllium grades are accumulated under un-irradiated. Additionally, irradiation tests have been prepared and development of PIE technologies has been performed. In this paper, the results of various properties and irradiation test plan for lifetime expansion of beryllium are described for material testing reactors.
Dorn, C. K.*; Tsuchiya, Kunihiko; Hatano, Yuji*; Chakrov, P.*; Kodama, Mitsuo*; Kawamura, Hiroshi
JAEA-Conf 2011-003, p.93 - 97, 2012/03
The JMTR has used beryllium reflector since it began operation in 1968. Beryllium has been used as the reflector element material in the reactor, specifically S-200F structural grade beryllium in JMTR. As a part of the reactor upgrade, the Japan Atomic Energy Agency (JAEA) has carried out the cooperation experiments to extend the operating lifetime of the beryllium reflector elements. Thus, three kinds of beryllium metals such as S-200F, S-65H and I-220H were selected at the viewpoints of production methods, impurities and grain size of beryllium starting powders, mechanical properties. Now, data of the material properties of these beryllium grades are accumulated under un-irradiated and irradiated conditions. In this paper, the results of various properties and irradiation test plan for lifetime expansion of beryllium are described for material testing reactors.
Longhurst, G. R.*; Tsuchiya, Kunihiko; Dorn, C.*; Folkman, S. L.*; Fronk, T. H.*; Ishihara, Masahiro; Kawamura, Hiroshi; Tranter, T. N.*; Rohe, R.*; Uchida, Munenori*; et al.
Nuclear Technology, 176(3), p.430 - 441, 2011/12
Times Cited Count：12 Percentile：66.82(Nuclear Science & Technology)Beryllium has important roles in nuclear facilities such as fission reactors and fusion reactors. Its neutron multiplication capability and low atomic weight make it very useful as a reflector in fission reactors. In both applications, the beryllium and the impurities in it become activated by neutrons transmutating to radionuclides, some of which are long-lived and difficult to dispose of. Also, gas production, notably helium and tritium, results in swelling, embrittlement, and cracking, which means that the beryllium must be replaced periodically, especially in fission reactors where dimensional tolerances must be maintained. It has long been known that neutron activation of inherent iron and cobalt in the beryllium results in significant 
Co activity. In 2001, it was discovered that activation of naturally occurring contaminants in the beryllium creates sufficient 
C and 
Nb to render the irradiated beryllium "Greater-Than-Class-C" for disposal in US radioactive waste facilities. In this paper we review the extent of the disposal issue, processes that have been investigated or considered for improving the disposability of irradiated beryllium, and approaches for recycling.
Shibayama, Tamaki*; Nakamichi, Masaru; Miyamoto, Mitsutaka*; Kuga, Noriyoshi*; Dorn, C. K.*; Knudson, T.*
Purazuma, Kaku Yugo Gakkai-Shi, 87(4), p.259 - 267, 2011/04
no abstracts in English
Tsuchiya, Kunihiko; Longhurst, G.*; Chakin, V.*; Tazhibayeva, I.*; Druyts, F.*; Dorn, C. K.*; Kawamura, Hiroshi
JAEA-Conf 2008-011, p.55 - 58, 2009/01
no abstracts in English
Dorn, C. K.*; Tsuchiya, Kunihiko; Hashiguchi, D. H.*; Sayer, A. B.*; Haws, W. J.*; Kawamura, Hiroshi
JAEA-Conf 2008-011, p.59 - 64, 2009/01
no abstracts in English
Tsuchiya, Kunihiko; Longhurst, G.*; Chakin, V.*; Tazhibayeva, I.*; Druyts, F.*; Dorn, C. K.*; Kawamura, Hiroshi
no journal, ,
Beryllium has been utilized as a moderator and/or reflector in a number of material testing reactors. In fact, the nuclear properties of beryllium are its low atomic number, low atomic weight, low parasitic capture cross section for thermal neutrons, readiness to part with one of its own neutrons (n, 2n), and good neutron elastic scattering characteristics. Various problems of beryllium utilization are introduced for nuclear reactors and two points are proposed for the solution of irradiated beryllium wastes. Thus, it will be necessary to consider fundamental changes to the frame design, starting with the choice of beryllium material grade. Additionally, irradiation tests are planned for the design modification of beryllium materials. Beryllium material grades are selected for material modification and irradiation tests have been discussed. New measurement procedures in PIEs are also proposed for evaluation of lifetime extension. In this presentation, status and future plan of beryllium reflector development are introduced.
Dorn, C. K.*; Tsuchiya, Kunihiko; Hatano, Yuji*; Chakrov, P.*; Kodama, Mitsuhiro*; Kawamura, Hiroshi
no journal, ,
no abstracts in English
