ANS / Publications / Journals / Nuclear Technology

Enhanced Thermal Expansion Control Rod Drive Lines for Passive Shutdown of Fast Reactors

Martin Edelmann, Walter Baumann, Alfred Bertram, Günter Kussmaul, Walter Väth

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 3-14

Technical Paper / Special on ANP ’92 Conference / Fission Reactor / dx.doi.org/10.13182/NT94-A34993

Negative Void Reactivity in a Large Liquid-Metal Fast Breeder Reactor with Hydrogenous Moderator (ZrH_1.7) Layers

Yoshiaki Oka, Tatjana Jevremovic, Sei-ichi Koshizuka

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 15-22

Technical Paper / Special on ANP ’92 Conference / Fission Reactor / dx.doi.org/10.13182/NT94-A34994

Comprehensive Analysis of Passive Safety Test Phase IIB in the Fast Flux Test Facility

Akira Yamaguchi, Hajime Niwa, Mitsuaki Yamaoka, Kazuyuki Tsukimori, Yoshio Shimakawa, Hisashi Ninokata, Kiyoto Aizawa

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 23-37

Technical Paper / Special on ANP ’92 Conference / Fission Reactor / dx.doi.org/10.13182/NT94-A34995

Design Study of the Deep-Sea Reactor X

Hiromasa Iida, Yuichi Ishizaka, Yeong-Chan Kim, Chouichi Yamaguchi

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 38-48

Technical Paper / Special on ANP ’92 Conference / Fission Reactor / dx.doi.org/10.13182/NT94-A34996

Conceptual Design Features for a Passive Light Water Cooled and Moderated Pressure Tube Reactor (PLPTR)

Jan Ru Tang, Neil E. Todreas, Michael J. Driscoll

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 49-62

Technical Paper / Special on ANP ’92 Conference / Fission Reactor / dx.doi.org/10.13182/NT94-A34997

Reflooding of Tight Lattice Bundles

Jean-Michel Veteau, Albert Digonnet, Roger Deruaz

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 63-71

Technical Paper / Special on ANP ’92 Conference / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34998

An Intelligent Man-Machine System for Future Nuclear Power Plants

Yoji Takizawa, Yoshiaki Hattori, Juichiro Itoh, Akira Fukumoto

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 72-82

Technical Paper / Special on ANP ’92 Conference / Human Factor / dx.doi.org/10.13182/NT94-A34999

Evaluation Program of the Integrated Surveillance and Control System ISACS—An Advanced Control Room Prototype

Conny B. O. Holmstroem, Tor Endestad, Knut Follesoe, Nils T. Foerdestroemmen, Kjell Haugset, Frode Strand Volden

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 83-92

Technical Paper / Special on ANP ’92 Conference / Reactor Control / dx.doi.org/10.13182/NT94-A35000

The Startup of the Dodewaard Natural Circulation Boiling Water Reactor—Experiences

Wim H. M. Nissen, Jaap Van Der Voet, Jadranko Karuza

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 93-102

Technical Paper / Special on ANP ’92 Conference / Nuclear Reactor Safety / dx.doi.org/10.13182/NT107-93

Pressurized Water Reactor Steam Line Break Analysis by Means of Coupled Three-Dimensional Neutronic, Three-Dimensional Core Thermohydraulic, and Fast Running System Codes

Hyun-Jong Paik, Patrick Raymond

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 103-111

Technical Paper / Special on ANP ’92 Conference / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35002

Monitoring Feedwater Flow Rate and Component Thermal Performance of Pressurized Water Reactors by Means of Artificial Neural Networks

Kadir Kavaklioglu, Belle R. Upadhyaya

Nuclear Technology / Volume 107 / Number 1 / July 1994 / Pages 112-123

Technical Paper / Special on ANP ’92 Conference / Reactor Control / dx.doi.org/10.13182/NT94-A35003

Consistent Generation and Functionalization of One-Dimensional Cross Sections for TRAC-BF1

José Luis Muñoz-Cobo, Gumersindo Verdú, Claubia Pereira, Alberto Escrivá, José Ródenas, Felix Castrillo, Juan Serra

Nuclear Technology / Volume 107 / Number 2 / August 1994 / Pages 125-137

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A34983

Qualification of the Taiwan Power Company’s Pressurized Water Reactor Physics Methods Using CASMO-3/SIMULATE-3

Ping-Hue Huang, Jing-Tong Yang

Nuclear Technology / Volume 107 / Number 2 / August 1994 / Pages 138-154

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A34984

Hybrid Thermionic Space Reactors for Power and Propulsion

Sümer Şahin, Elliot B. Kennel

Nuclear Technology / Volume 107 / Number 2 / August 1994 / Pages 155-181

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A34985

A New Fuel Material for Once-Through Weapons Plutonium Burning

Hiroshi Akie, Tadasumi Muromura, Hideki Takano, Shojiro Matsuura

Nuclear Technology / Volume 107 / Number 2 / August 1994 / Pages 182-192

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT107-182

Methods for the Determination of the In-Phase and Out-of-Phase Stability Characteristics of a Boiling Water Reactor

Tim H. J. J. Van Der Hagen, Imre Pázsit, Ola Thomson, Bengt Melkerson

Nuclear Technology / Volume 107 / Number 2 / August 1994 / Pages 193-214

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34987

Special Concrete Shield Selection Using the Analytic Hierarchy Process

Waleed H. Abulfaraj

Nuclear Technology / Volume 107 / Number 2 / August 1994 / Pages 215-226

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT94-A34988

Parametric Study of Recriticality in a Boiling Water Reactor Severe Accident

Bassam I. Shamoun, Robert J. Witt

Nuclear Technology / Volume 107 / Number 2 / August 1994 / Pages 227-235

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34989

Noise Analysis Method for Monitoring the Moderator Temperature Coefficient of Pressurized Water Reactors: Neural Network Calibration

J. R. Thomas, Jr., Joseph T. Adams

Nuclear Technology / Volume 107 / Number 2 / August 1994 / Pages 236-240

Technical Note / Reactor Operation / dx.doi.org/10.13182/NT94-A34990

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