Disposal of Aluminum Based Spent Fuels in a Repository

Disposal of Aluminum Based Spent Fuels in a Repository

著者名:

掲載資料名:

Scientific basis for nuclear waste management XIX : symposium held November 27-December 1, 1995, Boston, Massachusetts, U.S.A.

シリーズ名:

Materials Research Society symposium proceedings

シリーズ巻号:

412

発行年:

1996

開始ページ:

91

出版情報:

Pittsburgh, Pa.: MRS - Materials Research Society

ISSN:

02729172

ISBN:

9781558993150 [1558993150]

言語:

英語

請求記号:

M23500/412

資料種別:

国際会議録

詳細

TDL書誌ID:	ZA00019835
シリーズID:	PA00000011
会議名:	Symposium on scientific basis for nuclear waste management
回次:	19th
会議開催地:	Boston, MA, USA
会議開催年:	1995.11.27-1995.12.01

類似資料:

1 国際会議録 Scientific Basis for Storage Criteria for Interim Dry Storage of Aluminum-Clad Fuels Sindelar, R. L., Peacock, H. B., Jr., Lam, P. S., Iyer, N. C., Louthan, M. R., Jr., Murphy, J. R. MRS - Materials Research Society	7 国際会議録 Application of smart materials/technology at the Savannah River site Dunn,K.A., Louthan,M.R., Iyer,N.C., Giurgiutiu,V., Petrou,M.F., Laub,D.E. SPIE - The International Society for Optical Engineering
2 国際会議録 The Melt-Dilute Treatment of Al-Base Highly Enriched DOE Spent Nuclear Fuels: Principles and Practices Adams, T. M., Peacock, H. B., Jr., Rhode, F. C., Iyer, N. C. Materials Research Society	8 国際会議録 CARBON-14 IN WASTE PACKAGES FOR SPENT FUEL IN A TUFF REPOSITORY Van Konynenburg, R. A., Smith, C. F., Culham, H. W., Smith, H. D. Materials Research Society
3 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	9 国際会議録 Reactive Transport Modeling of Radionuclide Source-Terms in an Underground Spent Fuel Disposal Windt, L.De, Catalette, H., Gras, J.M. Materials Research Society
4 国際会議録 BEHAVIOR OF CARBON-14 IN WASTE PACKAGES FOR SPENT FUEL IN A REPOSITORY IN TUFF Van Konynenburg, R. A., Smith, C. F., Culham, H. W., Otto Jr., C. H Materials Research Society	10 国際会議録 EVALUATION OF SPENT FUEL AS A WASTE FORM IN A SALT REPOSITORY Gray, W. J., McVay, G. L., Barner, J. O, Shade, J. W., Cote, R. W. North-Holland
5 国際会議録 Disposal of Spent Sealed Radiation Sources in Borehole Repositories Sobolev, I. A., Timofeev, E. M., Ojovan, M. I., Shiryaev, V. V., Arustamov, A. E., Kachalov, M. B. MRS - Materials Research Society	11 国際会議録 *SPENT FUEL AS A WASTE FORM--DATE NEEDS TO ALLOW LONG TERM PERFORMANCE ASSESSMENT UNDER REPOSITORY DISPOSAL CONDITIONS Oversby, V. M. Materials Research Society
6 国際会議録 Room at the Mountain: Estimated Maximum Amounts of Commerical Spent Nuclear Fuel Capable of Disposal in a Yucca Mountain Repository John H. Kessler, Michael J. Apted, Wei Zhou, John Kemeny, Fraser King, Alan M. Ross, Benjamen Ross, Franklin W. Schwartz American Society of Mechanical Engineers	12 国際会議録 Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage R. E. Einziger, H. C. Tsai, M. C. Billone, B. A. Hilton American Society of Mechanical Engineers

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