ANS / Publications / Journals / Nuclear Technology

Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel

Bryan L. Broadhead

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 1-21

Technical Paper / Burnup Credit / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A35092

Evaluation of Burnup Credit for Fuel Storage Analysis—Experience in Spain

Joé M. Conde, Manuel Recio

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 22-32

Technical Paper / Burnup Credit / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35093

Burnup Credit Experiences with the GA-4 Cask

Jack K. Boshoven

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 33-39

Technical Paper / Burnup Credit / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35094

Study on the Criticality Safety Evaluation Method for Burnup Credit in JAERI

Yoshitaka Naito, Makoto Takano, Masayoshi Kurosawa, Takenori Suzaki

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 40-52

Technical Paper / Burnup Credit / Nuclear Crticality Safety / dx.doi.org/10.13182/NT95-A35095

Validation of SCALE-4 for Burnup Credit Applications

Stephen M. Bowman, Mark D. DeHart, Cecil V. Parks

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 53-70

Technical Paper / Burnup Credit / Nuclear Crticality Safety / dx.doi.org/10.13182/NT95-A35096

Three-Dimensional PDQ Validation for Calculating Core Parameters of a Uranium-Aluminide-Fueled Test Reactor

Soon Sam Kim, Jerry L. Judd

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 71-85

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35097

Assessment of a Nuclear Fuel Assembly Performance with Different Inner Water Channels

Gustavo Alonso-Vargas, José L. Montes, Mario R. Perusquía

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 86-92

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35098

A Comparison of Two Versions of a Proposed Test Reactor Using the MCNP Neutronics Code

Salim N. Jahshan, William K. Terry

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 93-105

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35099

Distribution of ¹⁶N and ¹⁹O in the Reactor Pool Water of the THOR Facility

Chien Chung, Cheng-Chang Chan

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 106-114

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35100

Preliminary Investigation of Actinide and Xenon Reactivity Effects in Accelerator Transmutation of Waste High-Flux Systems

Kenneth R. Olson, Douglass L. Henderson, Michael L. Woosley, Jr., William C. Sailor

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 115-131

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35101

Hybrid Simulation of Boiling Water Reactor Dynamics Using a University Research Reactor

James A. Turso, Robert M. Edwards, Jose March-Leuba

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 132-144

Nuclear Reactor Safety / Burnup Credit / dx.doi.org/10.13182/NT95-A35102

Oxidation/Corrosion of Nb-1 Zr and PWC-11 in Lithium for Space Reactor Applications

James R. DiStefano, James W. Hendricks

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 145-158

Material / Burnup Credit / dx.doi.org/10.13182/NT95-A35103

Sodium-Immersed Self-Cooled Electromagnetic Pump Design and Development of a Large-Scale Coil for High Temperature

Akihiro Oto, Nobuyuki Naohara, Masayoshi Ishida, Toshitaka Kuroki, Kenji Katsuki, Ryouji Kumazawa

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 159-167

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A35115

Monte Carlo Calculations for Recriticality During the Reflood Phase of a Severe Accident in a Boiling Water Reactor

Russell D. Mosteller, Frank J. Rahn

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 168-180

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35116

Modeling Fission Product Vapor Transport in the Falcon Facility

Iain M. Shepherd, Yannis Drossinos, Christopher G. Benson

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 181-197

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35117

Application of Nonlinear Nodal Diffusion Generalized Perturbation Theory to Nuclear Fuel Reload Optimization

G. Ivan Maldonado, Paul J. Turinsky

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 198-219

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35118

Design of a Mixer Settler Plant for Isotope Separation by Chemical Exchange

David A. White, Fathurrachman

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 220-227

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT95-A35119

Artificial Neural Networks Optimization Method for Radioactive Source Localization

Eitan Wacholder, Ezra Elias, Yoram Merlis

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 228-237

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A35120

Movement of a Redox Front Around a Repository for High-Level Nuclear Waste

Leonardo Romero, Luis Moreno, Ivars Neretnieks

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 238-249

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A35121

Application of Hydrogen Water Chemistry to Moderate Corrosive Circumstances Around the Reactor Pressure Vessel Bottom of Boiling Water Reactors

Shunsuke Uchida, Eishi Ibe, Kiyatomo Nakata, Motomasa Fuse, Katsumi Ohsumi, Yoshie Takashima

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 250-257

Technical Paper / Material / dx.doi.org/10.13182/NT95-A35122

A Radiometric Water-Level Monitoring System in a High-Pressure Steam Chamber and its Error Analysis

Beicheng Lee, Yuhua Ma, Shengming Jia, Nianzu Lee

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 258-262

Technical Paper / Radioisotope and Isotope / dx.doi.org/10.13182/NT95-A35123

Numerical Analysis of Buoyancy-Driven Exchange Flow with Regard to an HTTR Air Ingress Accident

Motoo Fumizawa, Tomoaki Kunugi, Makoto Hishida, Mikio Akamatsu, Sadao Fujii, Minoru Igarashi

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 263-272

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35124

On Microwave Experiments in Dielectric Media to Simulate Nuclear Volumetric Heating

Cameron R. Bass, Houston G. Wood III

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 273-284

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35125

Self-Tuning Control of a Nuclear Reactor Using a Gaussian Function Neural Network

Moon Ghu Park, Nam Zin Cho

Nuclear Technology / Volume 110 / Number 2 / May 1995 / Pages 285-293

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT95-A35126

Accelerator Transmutation of Waste Economics

Robert A. Krakowski

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 295-320

Technical Paper / Actinide Burning and Transmutation Special / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35105

Parametric Systems Studies of the Aqueous-Based (Slurry) Blanket Concept for Accelerator Transmutation of Waste

Carl A. Beard, J. Wiley Davidson, Robert A. Krakowski, Morris E. Battat

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 321-356

Technical Paper / Actinide Burning and Transmutation Special / Nuclear Fuel Cycles / dx.doi.org/10.13182/NT95-A35106

Pyrometallurgical Reprocessing of Fast Reactor Metallic Fuel—Development of A New Electrorefiner with A Ceramic Partition

Tadafumi Koyama, Reiko Fujita, Masatoshi Hzuka, Yukio Sumida

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 357-368

Technical Paper / Actinide Burning and Transmutation Special / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT95-A35107

Preliminary Analysis of the Induced Structural Radioactivity Inventory of the Base-Case Aqueous Accelerator Transmutation of Waste Reactor Concept

Judith A. Bezdecny, Kevin M. Vance, Douglass L. Henderson

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 369-395

Technical Note / Actinide Burning and Transmutation Special / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35108

Fuel Particle Failure Probabilities and Material Strengths Determined from Crush Test Data

Gregory K. Miller, Derek C. Wadsworth

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 396-406

Technical Paper / Actinide Burning and Transmutation Special / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35109

In-Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel

Theodore H. Bauer, John W. Holland

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 407-421

Technical Paper / Actinide Burning and Transmutation Special / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35110

Application of High-Frame-Rate Neutron Radiography with A Steady Thermal Neutron Beam to Two-Phase Flow Measurements in A Metallic Rectangular Duct

Takashi Hibiki, Kaichiro Mishima, Masahito Matsubayashi

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 422-435

Technical Paper / Actinide Burning and Transmutation Special / Radiation Application / dx.doi.org/10.13182/NT95-A35111

Nuclear Power Plant Transient Diagnostics Using Artificial Neural Networks That Allow “Don’t-Know” Classifications

Yair bartal, Jie Lin, Robert E. Uhrig

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 436-449

Technical Paper / Actinide Burning and Transmutation Special / Reactor Control / dx.doi.org/10.13182/NT95-A35112

Preliminary Neutronics Investigation of the Delayed Neutron Nondestructive Assay of an Integral Fast Reactor Waste Canister

C.-W. Wu, D. L. Henderson, E. F. Bennett

Nuclear Technology / Volume 110 / Number 3 / June 1995 / Pages 450-454

Department / Actinide Burning and Transmutation Special / Corrigendum / dx.doi.org/10.13182/NT95-A35113