The Design and Fabrication of the Transfer Canister for Spent Nuclear Fuel at the BN-350 Fast Reactor

The Design and Fabrication of the Transfer Canister for Spent Nuclear Fuel at the BN-350 Fast Reactor

著者名:

掲載資料名:

Nuclear fuel cycle, spent fuel, and radwaste management, codes, standards, and regulatory issues : presented at 8th International Conference on Nuclear Engineering, Baltimore, Maryland, April 2-6, 2000

シリーズ名:

ASME Symposia Volumes

シリーズ巻号:

ICONE 8(4)

発行年:

2000

巻:

4

ペーパー番号:

ICONE8-8398

開始ページ:

221

終了ページ:

228

総ページ数:

8

出版情報:

New York: American Society of Mechanical Engineers

ISBN:

9780791835036 [0791835030]

言語:

英語

請求記号:

A11658/8

資料種別:

国際会議録

詳細

TDL書誌ID:	ZA00048656
シリーズID:	PA00000270
会議名:	International Conference on Nuclear Engineering
回次:	8th
会議開催地:	Baltimore, Maryland, USA
会議開催年:	2000.04.02-2000.04.06

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1 国際会議録 The Design and Installation of a Spent Fuel Packaging Cask for the BN-350 Reactor K. J. Allen, L. J. Christensen, M. J. Shannon, F. A. Orren, K. E. Rosenberg, E. A. Howden American Society of Mechanical Engineers	7 国際会議録 Lab-Scale Demonstration of the Urex+1a Process Using Spent Nuclear Fuel Candido Pereira, George F. Vandegrift, Monica C. Regalbuto, Allen J. Bakel, Delbert L. Bowers American Institute of Chemical Engineers
2 国際会議録 Integrated Testing of a Drying Station for Spent Nuclear Fuel for the BN-350 Fast Reactor C. E. Baily, K. E. Rosenberg, K. J. Allen, E. A. Howden 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 Recent Progress on the Standardized DOE Spent Nuclear Fuel Canister D. Keith Morton, Spencer D. Snow, Tom E. Rahl, Tom J. Hill, Richard P. Morissette American Society of Mechanical Engineers	9 国際会議録 A Comparative Evaluation of Licensing Requirements for Dry Storage of Spent Nuclear Fuel in the United States, Germany, Canada and the Russian Federation Edward Wonder, David S. Duncan, Eric A. Howden American Society of Mechanical Engineers
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6 国際会議録 Assembly and Fuel Pin Irradiation Behavior in the BN-350 Fast Reactor V. N. Karaulov, A. R. Blynski, I. L. Yakovlev, S. V. Golovin, J. D. B. Lambert American Society of Mechanical Engineers	12 国際会議録 Corrosion Testing of a Simulated Five-Metal Epsilon Particle in Spent Nuclear Fuel Wronkiewicz, D.J., Watkins, C.S., Baughman, A.C., Miller, F.S., Wolf, S.F. Materials Research Society

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