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Volume 56

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Number 1

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-1

Number 2

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-A32867

Number 3

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-A32918