Home / Publications / Journals / Nuclear Technology / Volume 56 / Number 1

Volume 56

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)
Multiphase Transport Fundamentals, Reactor Safety Applications(Barry Ganapol)
Radiological Significance and Management of Tritium, Carbon-14, Krypton-85, Iodine-129 Arising from the Nuclear Fuel Cycle(Geoffrey G. Eichholz)

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