THE ASSESSMENT OF THE LONG-TERM EVOLUTION OF THE SPENT NUCLEAR FUEL MATRIX BY KINETIC, THERMODYNAMIC AND SPECTROSCOPIC STUDIES OF URANIUM MINERALS

THE ASSESSMENT OF THE LONG-TERM EVOLUTION OF THE SPENT NUCLEAR FUEL MATRIX BY KINETIC, THERMODYNAMIC AND SPECTROSCOPIC STUDIES OF URANIUM MINERALS

著者名:

Bruno, Jordi

掲載資料名:

Scientific basis for nuclear waste management XVIII : symposium held October 23-27, 1994, Kyoto, Japan

シリーズ名:

Materials Research Society symposium proceedings

シリーズ巻号:

353

発行年:

1995

開始ページ:

633

出版情報:

Pittsburgh, Pa.: MRS - Materials Research Society

ISSN:

02729172

ISBN:

9781558992535 [1558992537]

言語:

英語

請求記号:

M23500/353

資料種別:

国際会議録

詳細

TDL書誌ID:	ZA00020299
シリーズID:	PA00000011
会議名:	Symposium on scientific basis for nuclear waste management
回次:	18th
会議開催地:	Kyoto, Japan
会議開催年:	1994.10.23-1994.10.27

類似資料:

1 国際会議録 KINETIC STUDIES OF NATURAL URANIUM MINERALS FOR THE LONG-TERM EVOLUTION OF SPENT NUCLEAR FUEL UNDER OXIDIZING CONDITIONS Casas, Ignasi, Cera, E., Bruno, J. Materials Research Society	7 国際会議録 Modeling of the Spent Fuel Dissolution Rate Evolution for Repository Conditions: Matrix Alteration Model Results and Sensitivity Analysis Quinones, J., Iglesias, E., Martinez-Esperza, A., Merino, J., Cera, E., Bruno, J., de Pablo, J., Casas, I., Gimenez, J., … Materials Research Society
2 国際会議録 Uranium-Series Ages of Secondary Uranium Minerals with Applications to the Long-Term Evolution of Spent Nuclear Fuel Finch, R. J., Suksi, J., Rasilainen, K., Ewing, R. C. MRS - Materials Research Society	8 国際会議録 PERFORMANCE ASSESSMENT OF GLASS AS A LONG-TERM BARRIER TO THE RELEASE OF RADIONUCLIDES INTO THE ENVIRONMENT Grambow, B., Lutze, W., Ewing, R.C., Werme, L.O. Materials Research Society
3 国際会議録 Dissolution Studies of Soddyite as a Long-Term Analogue of the Oxidative Alteration of the Spent Nuclear Fuel Matrix Perez, I., Casas, I., Torrero, M. E., Cera, E., Duro, L., Bruno, J. MRS - Materials Research Society	9 国際会議録 Application of Interaction Matrices in Performance Assessment - The Fuel Matrix as an Example Sellin, Patrik, Bruno, Jordi, Cera, Ester MRS - Materials Research Society
4 国際会議録 URANIUM (IV) DIOXIDE AND SIMFUEL AS CHEMICAL ANALOGUES OF NUCLEAR SPENT FUEL MATRIX DISSOLUTION. A COMPARISON OF DISSOLUTION RESULTS IN A STANDARD NaCl/NaHCO3 … Bruno, Jordi, Casas, I., Cera, E., Pablo, J. de, Gimenez, J., Torrero, M. E. MRS - Materials Research Society	10 国際会議録 THE LONG-TERM STABILITY OF BECQUERELITE Finch, R. J., Suksi, J., Rasilainen, K., Ewing, R. C. MRS - Materials Research Society
5 国際会議録 A Kinetic Model for the Stability of the Spent Fuel Matrix Under Oxic Conditions: Model Development Against Experimental Evidence Bruno, Jordi, Cera, E., Duro, L., Eriksen, T. E., Sellin, P., Spahiu, K., Werme, L.O. MRS - Materials Research Society	11 国際会議録 Further Developments of the Reductive Capacity Model for Spent Fuel Stability: Application to Minor Radionuclides Bruno, J., Cera, E., Duro, L., Spahiu, K., Eriksen, T., Eklund, U-B., Werme, L. O. MRS - Materials Research Society
6 国際会議録 *Fabrication and testing of copper canister for long-term isolation of spent nuclear fuel Werme, L. O. MRS-Materials Research Society	12 国際会議録 Radiolytic Modeling: Application to Spent Fuel Dissolution Experiments Merino, Juan, Cera, Esther, Bruno, Jordi Materials Research Society

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