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Number 1

Table of Contents
Authors (A. J. Moorhead, R. W. McCulloch, R. N. Clark, B. Campbell, Andrew Richard Raymond Telford, Hsiang-Shou Cheng, David J. Diamond, J. V. Massey, A. Schneider, P. Silvennoinen, J. Vira, R. Westerberg, R. Förthmann, Thomas H. Pigford, J. Hadermann, Lawrence R. Scherpereel, Fred J. Frank, P. J. Fehrenbach, P. A. Morel, R. D. Sage, Masami Yajima, Naoaki Takashima, Sadaaki Sasaki, Satsuharu Takimoto, Bernhard Brand, Hans-Peter Gaul, Janardan Sarkar, Paul Robershotte, Peter Griffith, A. De Volpi, C. L. Fink, G. E. Marsh, E. A. Rhodes, G. S. Stanford)
Comments on “Realistic Estimates of the Consequences of Nuclear Accidents” (Peter Cybulskis, Paul Baybutt, James A. Gieseke, Richard S. Denning)
Reply to “Comments on ‘Realistic Estimates of the Consequences of Nuclear Accidents’” (Milton Levenson, Frank J. Rahn)
Continuing Comments on “The Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input” (David C. Cox, Paul Baybutt, Robert E. Kurth)
Reply to “Continuing Comments on ‘The Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input’” (D. H. Nguyen)
Radiological Significance and Management of Tritium, Carbon-14, Krypton-85, Iodine-129 Arising from the Nuclear Fuel Cycle (Geoffrey G. Eichholz)
Multiphase Transport Fundamentals, Reactor Safety Applications (Barry Ganapol)

Joining Techniques for Core Flow Test Loop Fuel Rod Simulators
A. J. Moorhead, R. W. McCulloch
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 7-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32876
Instrument Fault Detection in a Pressurized Water Reactor Pressurizer
R. N. Clark, B. Campbell
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 23-32
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32877
Measurements and Calculations of the Fuel Temperature Coefficient of Reactivity for the Hinkley Point ‘B’ Advanced Gas-Cooled Reactor
Andrew Richard Raymond Telford
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 33-39
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32878
Analyzing the Rod Drop Accident in a Boiling Water Reactor
Hsiang-Shou Cheng, David J. Diamond
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 40-54
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32879
The Role of Plutonium-238 in Nuclear Fuel Cycles
J. V. Massey, A. Schneider
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 55-71
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32880
Optimization of Fuel Cycle Strategies with Constraints on Uranium Availability
P. Silvennoinen, J. Vira, R. Westerberg
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 72-80
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32881
Irradiation Performance of Coated Fuel Particles with Fission Product Retaining Kernel Additives
R. Förthmann
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 81-92
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32882
Migration of Brine Inclusions in Salt
Thomas H. Pigford
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 93-101
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32883
The Influence of Speciation on the Geospheric Migration of Radionuclides
J. Hadermann
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 102-105
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32884
Fuel Cycle Cost Considerations of Increased Discharge Burnups
Lawrence R. Scherpereel, Fred J. Frank
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 106-111
Technical Paper | Economic | doi.org/10.13182/NT82-A32885
In-Reactor Measurement of Cladding Strain: Fuel Density and Relocation Effects
P. J. Fehrenbach, P. A. Morel, R. D. Sage
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 112-119
Technical Paper | Material | doi.org/10.13182/NT82-A32886
The Effect of Residual Decontamination Reagent on Stress Corrosion Cracking of Austenitic Materials Under High Temperature Water
Masami Yajima, Naoaki Takashima, Sadaaki Sasaki, Satsuharu Takimoto
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 120-127
Technical Paper | Material | doi.org/10.13182/NT82-A32887
Influence of Partial Blockage of a BWR Bundle on Heat Transfer, Cladding Temperature, and Quenching During Bottom Flooding or Top Spraying Under Simulated LOCA Conditions
Bernhard Brand, Hans-Peter Gaul, Janardan Sarkar
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 128-133
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32888
Downflow Post-Critical Heat Flux Heat Transfer to Low Pressure Water
Paul Robershotte, Peter Griffith
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 134-140
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32889
Fast-Neutron Hodoscope at TREAT: Methods for Quantitative Determination of Fuel Dispersal
A. De Volpi, C. L. Fink, G. E. Marsh, E. A. Rhodes, G. S. Stanford
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 141-188
Technical Paper | Analyses | doi.org/10.13182/NT82-1

Number 2

Table of Contents
Authors (D. E. Clark, L. Urwongse, C. Maurer, David G. Coles, Fernando Bazan, L. H. Johnson, D. W. Shoesmith, G. E. Lunansky, M. G. Bailey, P. R. Tremaine, R. P. Schuman, Joseph H. Simmons, Aaron Barkatt, Pedro B. Macedo, Aaron Barkatt, Alisa Barkatt, Pehr E. Pehrsson, Pedro B. Macedo, Joseph H. Simmons, C. R. Kennedy, K. F. Flynn, R. M. Arons, J. T. Dusek, Barry E. Scheetz, William B. White, Scott D. Atkinson, Claudio Pescatore, Albert J. Machiels, B. A. Staples, B. E. Paige, D. W. Rhodes, M. W. Wilding, D. M. Strachan, R. P. Turcotte, B. O. Barnes, P. A. Pizzica, H. H. Hummel, R. J. LaBauve, T. R. England, D. C. George, C. W. Maynard, R. E. Williford, D. D. Lanning, C. L. Mohr, A. Knoll, A. Notea, Y. Segal, J. O. Blomeke, A. G. Croff, Seyyed Nejat, Nicholas Tsoulfanidis, Robert C. Sanders, H. G. Groehn, Vikram N. Patel, J. N. Anno)
Preface: Comparative Leaching Behavior of Radioactive Waste Forms (Martin G. Seitz)
Overview: Argonne Workshop on Comparative Leaching Behavior of Radioactive Waste Forms (A. M. Friedman)
Thermal Analysis of Pressurized Water Reactors (K. Almenas)
Physics of Modern Materials (Vols. I and II) (J. C. Corelli)
Nuclear Disaster in the Urals (Dennis D. Patton)
Two-Phase Flow and Heat Transfer in the Power and Process Industries (Gary A. Pertmer)
Theory of the Nuclear Shell Model (D. A. Bromley)
Basic Elements of Light Water Reactor Fuel Rod Design (Joel Weisman, Roy Eckart)

Application of Glass Corrosion Concepts to Nuclear Waste Immobilization
D. E. Clark, L. Urwongse, C. Maurer
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 212-225
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32849
Continuous-Flow Leaching Studies of Crushed and Cored SYNROC
David G. Coles, Fernando Bazan
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 226-237
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32850
Mechanisms of Leaching and Dissolution of UO₂ Fuel
L. H. Johnson, D. W. Shoesmith, G. E. Lunansky, M. G. Bailey, P. R. Tremaine
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 238-253
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32851
Leach Testing of Idaho Chemical Processing Plant Final Waste Forms
R. P. Schuman
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 254-264
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32852
Mechanisms That Control Aqueous Leaching of Nuclear Waste Glass
Joseph H. Simmons, Aaron Barkatt, Pedro B. Macedo
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 265-270
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32853
The Importance of CO₂ Buffering and of the Total Ionic Balance in Measurements on the Durability of Glasses
Aaron Barkatt, Alisa Barkatt, Pehr E. Pehrsson, Pedro B. Macedo, Joseph H. Simmons
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 271-277
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32854
Comparative Leaching Behavior of SYNROC B and A Borosilicate Glass
C.R. Kennedy, K. F. Flynn, R. M. Arons, J. T. Dusek
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 278-288
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32855
Dissolution of Aluminum-, Titanium-, and Zirconium-Based Crystalline Waste Form Components Under Hydrothermal Conditions
Barry E. Scheetz, William B. White, Scott D. Atkinson
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 289-296
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32856
A Criterion for Selecting Leach Test Specimen Sizes
Claudio Pescatore, Albert J. Machiels
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 297-300
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32857
Leaching Properties and Chemical Composition of Calcines Produced at the Idaho Chemical Processing Plant
B.A. Staples, B. E. Paige, D. W. Rhodes, M. W. Wilding
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 301-305
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32858
MCC-1: A Standard Leach Test for Nuclear Waste Forms
D.M. Strachan, R. P. Turcotte, B. O. Barnes
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 306-309
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32859
The Effect of Time Delays in Fuel Pin Failure on LOF-TOP Transient Calculations for a Commercial-Sized LMFBR
P. A. Pizzica, H. H. Hummel
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 313-321
Nuclear Safety | doi.org/10.13182/NT82-A32860
Fission Product Analytic Impulse Source Functions
R. J. LaBauve, T. R. England, D. C. George, C. W. Maynard
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 322-339
Fuel Cycle | doi.org/10.13182/NT82-A32861
A Model for the Effective Thermal and Mechanical Properties of Cracked UO₂ Pellets
R. E. Williford, D. D. Lanning, C. L. Mohr
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 340-350
Nuclear Fuel | doi.org/10.13182/NT82-A32862
Probabilistic Interpretation of Nuclear Waste Assay by Passive Gamma Technique
A. Knoll, A. Notea, Y. Segal
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 351-360
Radioactive Waste Management | doi.org/10.13182/NT82-A32863
Nuclear Waste Partitioning and Transmutation
J. O. Blomeke, A. G. Croff
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 361-371
Radioactive Waste Management | doi.org/10.13182/NT82-A32864
The Effect of Plant Reliability Improvement in the Cost of Generating Electricity
Seyyed Nejat, Nicholas Tsoulfanidis, Robert C. Sanders
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 372-391
Economic | doi.org/10.13182/NT82-A32865
Estimate of Cross Flow in High Temperature Gas-Cooled Reactor Fuel Blocks
H. G. Groehn
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 392-400
Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32866
Radiation-Induced Outgassing from Sorption Pump Material
Vikram N. Patel, J. N. Anno
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Page 401
Technical Note | Material | doi.org/10.13182/NT82-A32867

Number 3

Table of Contents
Authors (L. Böhm, G. G. Loomis, R. W. Shumway, V. K. Chandola, S. K. Loyalka, James M Griffith, Michael A. Ross, Dale E. Klein, Tsutomu Hoshino, Tomonori Shirakawa, William A. Jester, Anthony J. Baratta, Jr., J. Louis Tylee, D. Saphier, J. T. Madell, Shahid Ahmed, A. A. Husseiny, I. Bernstein, J. S. Greacen, R. A. Matzie, D. D. Miller, Yu-Keung Sze, Leonard James Clegg, Andrew Francis Gerwing, George Robert Grant, C. C. Lee, R. A. Karam, G. L. Copeland, M. M. Martin, J. Rest, D. D. Lanning, Sridhar Komarneni, Rustum Roy, Tachimori Ohba, Satsuharu Takimoto, Yoshio Kitada, Tomio Tsunoda, Akira Kobayashi, Kenji Ishida, Ralph-D. von Dincklage)
Summary of the IAEA Specialists Meeting on Gas-Cooled Reactor Safety and Licensing Aspects (A. Goodjohn, J. Kupitz, G. Sarlos)
Theory of Meson Interactions with Nuclei (N. V. V. J. Swamy)
Computational Fluid Dynamics (Vol. 2) (Clarence E. Lee)
Nuclear Energy (2nd ed.) (Jerome G. Morse)
Introduction to Metallurgical Thermodynamics (2nd ed.) (Craig Shumaker)

On the Behavior of Impregnated Charcoal Filters During a Two-Stage Accident
L. Böhm
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 422-425
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32900
Transition Boiling Heat Transfer in the Semiscale Mod-3 Core During Reflood
G. G. Loomis, R. W. Shumway
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 426-433
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32901
Gap Conductance and Temperature Transients in Modified Pulse Design Experiments
V. K. Chandola, S. K. Loyalka
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 434-446
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32902
Power Estimation in the Pressurized Water Reactor
James M. Griffith
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 447-453
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32903
Synthetic Fuel Production Using Texas Lignite and a Very High Temperature Reactor for Process Heat
Michael A. Ross, Dale E. Klein
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 454-464
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32904
Load Follow Simulation of Three-Dimensional Boiling Water Reactor Core by PACS-32 Parallel Microprocessor System
Tsutomu Hoshino, Tomonori Shirakawa
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 465-477
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32905
Monitoring Krypton-85 During Three Mile Island Unit 2 Purging
William A. Jester, Anthony J. Baratta, Jr.
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 478-483
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A32906
A Generalized Likelihood Ratio Approach to Detecting and Identifying Failures in Pressurizer Instrumentation
J. Louis Tylee
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 484-492
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A32907
The DSNP Simulation Language and Its Application to Liquid-Metal Fast Breeder Reactor Transient Analyses
D. Saphier, J. T. Madell
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 493-506
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A32908
Risk Assessment of Alternative Proliferation Routes
Shahid Ahmed, A. A. Husseiny
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 507-515
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32909
An Evaluation of Pressurized Water Reactor Frequent Refueling
I. Bernstein, J. S. Greacen, R. A. Matzie, D. D. Miller
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 516-526
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32910
Oxidation of Pu(lll) by Nitric Acid in Tri-n-Butyl Phosphate Solutions. Part I. Kinetics of the Reaction and Its Effect on Plutonium Losses in Countercurrent Liquid-Liquid Extraction
Yu-Keung Sze, Leonard James Clegg, Andrew Francis Gerwing, George Robert Grant
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 527-534
Technical Paper | Chemical Processing | doi.org/10.13182/NT82-A32911
Metallic Combinations of Pu-Th and ²³³U-Th or Pu-Th and ²³³U-²³⁸U Fuel Cycles as Possible Alternatives to (Pu-U)O₂ in LMFBRs
C. C. Lee, R. A. Karam
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 535-546
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32912
Development of High-Uranium-Loaded U₃O₈-Al Fuel Plates
G. L. Copeland, M. M. Martin
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 547-552
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32913
The Prediction of Transient Fission-Gas Release and Fuel Microcracking Under Severe Core-Accident Conditions
J. Rest
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 553-564
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32914
The Possible Impact of Fuel Pellet Cracking on Inferred Gap Conductance and Fuel Stored Energy
D. D. Lanning
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 565-574
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32915
Interactions of Backfill Materials with Cesium in a Bittern Brine Under Repository Conditions
Sridhar Komarneni, Rustum Roy
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 575-579
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32916
Environmental Radiation Monitoring System Development for Atmospheric Plumes from Light Water Reactor Nuclear Power Plants
Tachimori Ohba, Satsuharu Takimoto, Yoshio Kitada, Tomio Tsunoda, Akira Kobayashi, Kenji Ishida
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 580-590
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT82-A32917
Determination of the Concentrations of Alpha-Emitting Isotopes
Ralph-D. Von Dincklage
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 591-593
Technical Note | Analyse | doi.org/10.13182/NT82-A32918

Volume 56

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