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Volume 62

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Number 1

The Abundance of Fission Gases in the Off Gas of a Boiling Water Reactor

H. W. Kalfsbeek

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 7-21

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33227

The Modular High-Temperature Reactor

Herbert Reutler, Günter H. Lohnert

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 22-30

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33228

An Analytical Study of a Small-Break Loss-of-Coolant Accident with Upper Head Injection

Mark T. Leonard

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 31-42

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33229

Simple Lake Breeze Front Position Technique for Off-Site Dose Assessment

Thomas J. Burda, Carl A. Mazzola

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 43-50

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33230

Modeling Fragmentation and Spallation of Oxide Reactor Fuel During Transient Heating Including the Effects of Burnup and Fission Product Distribution

Ronald J. DiMelfi, John M. Kramer

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 51-61

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33231

Heat Transfer from Transport Cask Storage Facilities for Spent Fuel Elements

Wolfgang von Heesen, Heinz Malmström, Rüdiger Detzer, Werner Loew

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 62-70

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33232

Evaluation of SrMoO4 in Repository Simulating Tests

Sridhar Komarneni, Rustum Roy, Della M. Roy

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 71-74

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33233

Irradiation Behavior of Pressurized Water Reactor Control Materials

Richard V. Demars, Charles G. Dideon, Thomas A. Thornton, James S. Tulenko, Wayne A. Pavinich, Elma Beth S. Pardue*

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 75-80

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33234

Dose Response in Radiation-Induced Human Carcinogenesis: Accumulated Data Do Not Yet Solve the Enigma

Werner Burkart

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 81-93

Technical Paper / Radiation Biology and Environment / dx.doi.org/10.13182/NT83-A33235

Statistical Characteristics of Incipient Two-Phase Noise for Reactor Diagnosis

Monideep Kumar De

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 94-101

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33236

Development and Operational Experiences of an Automated Remote Inspection System for Interior of Primary Containment Vessel of a BWR

Norihiko Ozaki, Fumio Tomizawa, Masaaiki Fujii, Masayoshi Sasaki, Ken-Ichiro Sadakane, Chikara Sato, Katsuhiro Mizuno

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 102-109

Technical Paper / Technique / dx.doi.org/10.13182/NT83-A33237

The Movement of a Redox Front Downstream from a Repository For Nuclear Waste

Ivars Neretnieks

Nuclear Technology / Volume 62 / Number 1 / July 1983 / Pages 110-115

]Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33238

Number 2

The Effect of Salt Composition on Reductive Extraction of Some Typical Elements from Molten LiF-BeF2 Salt into Liquid Bismuth

Hirotake Moriyama, Kunimitsu Yajima, Yasunobu Tominaga, Kimikazu Moritani, Jun Oishi

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 133-138

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33211

The Current Status and Perspectives of Fissile Material Availability in The World Through the Year 2000

John Jeffrey Stobbs, Antonio Matteo Taormina

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 139-144

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33212

Aqueous Corrosion of Uranium Aluminide Fuel

Krishna Vinjamuri, Richard R. Hobbins

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 145-150

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33213

The Effects of Surface Area to Solution Volume on Waste Glass Leaching

L. R. Pederson, C. Q. Buckwalter, G. L. McVay

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 151-158

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33214

Transient Analysis of the Three Mile Island Unit 2 Pressurizer System

Benaissa Baggoura, William R. Martin

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 159-171

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33215

Safety Analysis of the Reactivity Transients Resulting from Water Ingress into a High-Temperature Pebble Bed Reactor

Rahim Nabbi, Wilfried Jahn, Gerhard Meister, Werner Rehm

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 172-189

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33216

Analysis of Decommissioning Costs for Nuclear Power Reactors

David F. Greenwood, Richard K. Westfahl, James W. Rymsha

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 190-206

Technical Paper / Economic / dx.doi.org/10.13182/NT83-A33217

Analysis of Detailed Neutron Fluxes in a PWR Pressure Vessel by Two- and Three-Dimensional Pallas Transport Codes

Kiyoshi Takeuchi, Nobuo Sasamoto

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 207-221

Technical Paper / Analyse / dx.doi.org/10.13182/NT83-A33218

A Finite Difference Treatment of Differential Equation Systems with Widely Differing Time Constants

G. Ronald Dalton, Michael T. Gamble

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 222-226

Technical Paper / Analyse / dx.doi.org/10.13182/NT83-A33219

System Preparation and Fast Neutron Spectra Measurement in a Graphite Stack

Alex Tsechanski, Gad Shani

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 227-237

Technical Paper / Analyse / dx.doi.org/10.13182/NT83-A33220

Modified Fuel Assembly Design for Pressurized Water Reactors with Improved Fuel Utilization

Alex Galperin, Yigal Ronen

Nuclear Technology / Volume 62 / Number 2 / August 1983 / Pages 238-242

Technical Note / Fuel Cycle / dx.doi.org/10.13182/NT83-A33221

Number 3

  • Table of Contents
  • Authors(Mitsuo Kawaguchi, Kenkichi Ishigure, Norihiko Fujita, Keichi Oshima, Michael L. Corradini, Yigal Ronen, Dror Regev, Michael Boček, Claus Petersen, Lothar Schmidt, Jess M. Cleveland, Terry F. Rees, Kenneth L. Nash, A. G. Solomah, Sachio Fujine, Yuji Naruse, Koreyuki Shiba, Ed Von Halle, Houston G. Wood III, Ralph A. Lowry, Allen G. Croff, R. F. Domagala, T. C. Wiencek, H. R. Thresh, Kuo-Fu Chen, C. A. Olson, Tim E. Myrick, Michael S. Blair, Richard W. Doane, William A. Goldsmi)
  • Advances in Nuclear Physics, Vol. 12
  • McGraw-Hill Encyclopedia of Physics

Deposition of Model Crud on Boiling Zircaloy Surfaces at High Temperature

Mitsuo Kawaguchi, Kenkichi Ishigure, Norihiko Fujita, Keichi Oshima

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 253-262

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33249

A Transient Model for the Ablation and Decomposition of Concrete

Michael L. Corradini

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 263-273

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33250

High Converter Pressurized Water Reactor with Heavy Water as a Coolant

Yigal Ronen, Dror Regev

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 274-283

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT83-A33251

The Lifetime and Failure Strain Prediction of Zircaloy-4 Cladding Loaded Under Loca-Similar Temperature Ramp Conditions

Michael Boček, Claus Petersen, Lothar Schmidt

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 284-297

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33252

Plutonium Speciation in Selected Basalt, Granite, Shale, and Tuff Groundwaters

Jess M. Cleveland, Terry F. Rees, Kenneth L. Nash

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 298-310

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33253

Effects of Temperature on the Leaching Behavior of Sintered Modified Synroc-B Waste form

A. G. Solomah

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 311-316

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33254

Analysis of Uranium Isotope Separation by Redox Chromatography

Sachio Fujine, Yuji Naruse, Koreyuki Shiba

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 317-324

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT83-A33255

The Effect of Vacuum Core Boundary Conditions on Separation in the Gas Centrifuge

ED Von Halle, Houston G. Wood III, Ralph A. Lowry

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 325-334

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT83-A33256

ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials

Allen G. Croff

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 335-352

Technical Paper / Analyses / dx.doi.org/10.13182/NT83-1

U-Si and U-Si-Ai Dispersion Fuel Alloy Development for Research and Test Reactors

R. F. Domagala, T. C. Wiencek, H. R. Thresh

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 353-360

Technical Note / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33258

Analytic Solution to Verify Code Predictions of Two-Phase Flow in a Boiling Water Reactor Core Channel

Kuo-Fu Chen, C. A. Olson

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 361-363

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33259

A Mobile Gamma Scanning System for Detecting Radiation Anomalies

Tim E. Myrick, Michael S. Blair, Richard W. Doane, William A. Goldsmith

Nuclear Technology / Volume 62 / Number 3 / September 1983 / Pages 364-370

Technical Note / Technique / dx.doi.org/10.13182/NT83-A33260