The Melt-Dilute Treatment of Al-Base Highly Enriched DOE Spent Nuclear Fuels: Principles and Practices

The Melt-Dilute Treatment of Al-Base Highly Enriched DOE Spent Nuclear Fuels: Principles and Practices

著者名:

掲載資料名:

Scientific basis for nuclear waste management XXII : symposium held November 30-December 4, 1998, Boston, Massachusetts, U.S.A.

シリーズ名:

Materials Research Society symposium proceedings

シリーズ巻号:

556

発行年:

1999

開始ページ:

495

終了ページ:

504

総ページ数:

10

出版情報:

Pittsburgh, Pa.: Materials Research Society

ISSN:

02729172

ISBN:

9781558994621 [1558994629]

言語:

英語

請求記号:

M23500/556

資料種別:

国際会議録

詳細

TDL書誌ID:	ZA00014187
シリーズID:	PA00000011
会議名:	Symposium on scientific basis for nuclear waste management
回次:	22nd
会議開催地:	Boston, MA, USA
会議開催年:	1998.11.30-1998.12.04

類似資料:

1 国際会議録 Volatilization of fission products from metallic melts in the melt-dilute treatment technology development for Al-based DOE spent nuclear fuels Adams, Thad M., Duncan, Andrew J., Peacok, Harold B. Jr. MRS-Materials Research Society	7 国際会議録 ESTABLISHING A DISPOSITION STRATEGY FOR DOE-OWNED SPENT NUCLEAR FUEL Thompson, Jon H. American Institute of Chemical Engineers
2 国際会議録 The Development of Mobile Melt-Dilute Technology for the Treatment of Former Soviet Union Research Reactor Fuel D. A. Sell, E. A. Howden, K. J. Allen, K. Marsden, B. R. Westphal, H. B. Peacock, N. C. Iyer, D. L. Fisher, T. M. Adams, … American Society of Mechanical Engineers	8 国際会議録 Drop Testing of DOE Spent Nuclear Fuel Canisters American Society of Mechanical Engineers
3 国際会議録 Disposal of Aluminum Based Spent Fuels in a Repository Louthan, M. R., Jr., Iyer, N. C., Sindelar, R. L., Peacock, H. B., Jr. MRS - Materials Research Society	9 国際会議録 Technology Development for Nuclear Fuel Cycle: Radioactive Waste Treatment and Spent Fuel Storage M. Kikuchi, T. Yoshida, M. Matsuda, T. Izumida American Society of Mechanical Engineers
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5 国際会議録 Treatment of Spent Nuclear Fuel L-Basin Sludge Oji, L., Westover, B., Nichols, D., Martin, H. American Institute of Chemical Engineers	11 国際会議録 Corrosion Behavior of High Burnup Spent Fuel in Highly Alkaline Solutions A. Loida, R. Gens, V. Metz, K. Lemmens, C. Cachoir, T. Mennecart, B. Kienzler Materials Research Society
6 国際会議録 Can Spent Nuclear Fuel Decay Heat Prevent Radionuclide Release? Jerden, James L. Jr., Goldberg, Margaret M., Cunnane, James C., Bauer, Theodore H., Wigeland, Roald A., Nietert, Russell … Materials Research Society	12 国際会議録 National Overview of Spent Nuclear Fuel Vulnerabilities Resolution Cohlmeyer, A.S., Eckert, H.J., Smith, N.E. Lapple American Institute of Chemical Engineers

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