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Journal Articles

Progress of demonstration experiment on irradiation of vibro-packed MOX fuel assemblies in the BN-600 reactor

Mayorshin, A. A.*; Skiba, O. V.*; Bychkov, A. V.*; Kisly, V. A.*; Shishalov, O. V.*; Krukov, F. N.*; Novoselov, A. E.*; Markov, D. V.*; Green, P. I.*; Funada, Toshio; et al.

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 11 Pages, 2012/00

The paper presents progress results, including fabrication of vibropac MOX fuel pins and 21 FAs for fast reactor BN-600, irradiation parameters and PIE results. It is shown, that no violations of safe operation limits take place. The activities within the framework of the Demonstration experiment is based on the international cooperation and have been performed with the support and participation Russian and Japanese organizations RIAR, IPPE, OKBM, BNPP, MEXT, JAEA, PESCO. The goal of the experiment is to validate possibility of using vibropac MOX FA for weapon plutonium disposition.

Journal Articles

Development of a performance analysis code for vibro-packed MOX fuels

Ishii, Tetsuya; Nemoto, Junichi*; Asaka, Takeo; Sato, Seichi*; Mayorshin, A.*; Shishalov, O.*; Kryukov, F.*

Journal of Nuclear Science and Technology, 45(4), p.263 - 273, 2008/04

 Times Cited Count:2 Percentile:17.03(Nuclear Science & Technology)

In order to develop a vibro-packed MOX fuel performance analysis code, thermochemical and mechanical properties of the vibro-packed fuels were incorporated into a pellet type fuel performance analysis code CEDAR. Calculations were made by the developed code on a vibro-packed MOX fuel pin irradiated at BN-600 in Russia. Since the calculated results agreed well with the behaviors obtained from the experimental data, it can be concluded that the code was well modeled and qualitatively validated.

JAEA Reports

Irradiation limit test of ODS ferritic steels fuel pins in BOR-60,1

Kaito, Takeji; Ukai, Shigeharu; Seki, Masayuki; Mayorshin, A. A.*; O.V.SHISHALOV*

JNC TY9400 2003-032, 243 Pages, 2004/03

JNC-TY9400-2003-032.pdf:8.3MB

In order to confirm and demonstrate the ODS fuel pin integrity, the irradiation test has being carried out in the frame of Japan-Russian FBR cyclecooperation. The irradiation test in BOR-60 has started since June, 2003. The target burnup of this irradiation test is up to 150GWd/t.

Journal Articles

Development of ODS Ferritic Steel Cladding and its Irradiation Test in BOR-60

Kaito, Takeji; Ukai, Shigeharu; Seki, Masayuki; Mayorshin, A. A.*; V.SHISHALOV, Oleg*

Inter.Conf. NUCLEAR POWER AND FUEL CYCLES, 0 Pages, 2003/00

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