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Volume 107

Number 3

Radiation Damage in a Rock Salt Nuclear Waste Repository

Wim J. Soppe, Jan Prij

Nuclear Technology / Volume 107 / Number 3 / September 1994 / Pages 243-253

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35005

Low-Level Radioactive Hanford Wastes Immobilized by Cement-Based Grouts

Frank H. Huang, Dolores E. Mitchell, John M. Conner

Nuclear Technology / Volume 107 / Number 3 / September 1994 / Pages 254-271

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35006

Industrial Scale Removal of Cesium with Hexacyanoferrate Exchanger—Process Development

Risto Harjula, Jukka Lehto, Esko H. Tusa, Asko Paavola

Nuclear Technology / Volume 107 / Number 3 / September 1994 / Pages 272-278

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35007

Industrial Scale Removal of Cesium with Hexacyanoferrate Exchanger—Process Realization and Test Run

Esko H. Tusa, Asko Paavola, Risto Harjula, Jukka Lehto

Nuclear Technology / Volume 107 / Number 3 / September 1994 / Pages 279-284

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35008

Criticality Data and Validation Studies of Arrays of Mixed-Oxide Fuel Pins in Aqueous and Organic Solutions

Gary R. Smolen, Sidney R. Bierman, Nobuo Fukumura

Nuclear Technology / Volume 107 / Number 3 / September 1994 / Pages 285-303

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT94-A35009

Criticality Data and Validation Studies of Plutonium-Uranium Nitrate Solutions in Cylindrical and Slab Geometry

Gary R. Smolen, Raymond C. Lloyd, Hideyuki Funabashi

Nuclear Technology / Volume 107 / Number 3 / September 1994 / Pages 304-325

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT94-A35010

Criticality Data and Validation Studies of Plutonium-Uranium Nitrate Solutions in Annular Geometry

Gary R. Smolen, Raymond C. Lloyd, Tomozo Koyama

Nuclear Technology / Volume 107 / Number 3 / September 1994 / Pages 326-339

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT94-A35011

Criticality Data and Validation Studies of Mixed-Oxide Fuel Pin Arrays in Pu+U+Gd Nitrate

Gary R. Smolen, Raymond C. Lloyd, Tadakuni Matsumoto

Nuclear Technology / Volume 107 / Number 3 / September 1994 / Pages 340-355

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT94-A35012