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Volume 52

Number 2

Table of Contents
Authors(N. P. Bhat, H. U. Borgstedt, A. A. Emami, S. K. Loyalka, Wayne R. Meier, K. O. Ott, J. F. Marchaterre, R. A. Matzie, D. C. Leung, Y. Liu, R. W. Beekmann, Ahmed Badruzzaman, Martin Becker, J. A. Shields, Jr., Richard Simms, Stephen M. Gehl, Robert K. Lo, Alan B. Rothman, Ronald E. Bullock, Herbert E. Nuttall, Asit K. Ray, E. James Davis, E. R. Gilbert, B. A. Chin, J. A. Williams, W. Baxter, G. Collins, K. Harding, C. M. Leslie, R. J. Sills, T. D. Märk, M. Pahl, R. Vartanian, R. Chawla, J. C. Mailen, R. A. Lillie, R. T. Santoro, R. G. Alsmiller, Jr.)
Comments on “Application of Simplified Reliability Methods for Risk Assessment of Nuclear Waste Repositories”(Charles M. Koplik)
Reply to “Comments on ‘Application of Simplified Reliability Methods for Risk Assessment of Nuclear Waste Repositories’ ”(Andreas Pritzker)
Reaktorsicherheit(Adolf Birkhofer)
Advances in Nuclear Science and Technology
Plutonium Handbook
Thermodynamische Tabellen
Tables of Isotopes

Calibration of Electrochemical Oxygen Meters for Sodium in Static Tests and in the Sodium Loop

N. P. Bhat, H. U. Borgstedt

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 153-161

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32660

Role of Condensation in Aerosol Source Term for Liquid-Metal Fast Breeder Reactor Containments

A. A. Emami, S. K. Loyalka

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 162-169

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32661

Tritium Breeding Management in the High Yield Lithium Injection Fusion Energy Chamber

Wayne R. Meier

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 170-178

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32662

Statistical Evaluation of Design-Error Related Nuclear Reactor Accidents

K. O. Ott, J. F. Marchaterre

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 179-188

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT81-A32663

The Benefits of Cycle Stretchout in Pressurized Water Reactor Extended-Burnup Fuel Cycles

R. A. Matzie, D. C. Leung, Y. Liu, R. W. Beekmann

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 189-197

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT81-A32664

Simplified Procedures for Fast Reactor Fuel Cycle and Sensitivity Analysis

Ahmed Badruzzaman, Martin Becker

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 198-213

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT81-A32665

Bow in Experimental Breeder Reactor II Reflector Subassemblies

J. A. Shields, Jr.

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 214-227

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT81-A32666

TREAT Test L5 Simulating an LMFBR Loss-of-Flow Accident with FTR-Type Irradiated Fuel

Richard Simms, Stephen M. Gehl, Robert K. Lo, Alan B. Rothman

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 228-245

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT81-A32667

Full-Fluence Tests of Experimental Thermosetting Fuel Rods for the High-Temperature Gas-Cooled Reactor

Ronald E. Bullock

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 246-259

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT81-A32668

An Analysis of Diffusional Ion Transport in Ocean Sediments: Subseafloor Disposal of Radioactive Waste

Herbert E. Nuttall, Asit K. Ray, E. James Davis

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 260-272

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT81-A32669

In-Reactor Creep Measurements

E. R. Gilbert, B. A. Chin

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 273-283

Technical Paper / Material / dx.doi.org/10.13182/NT81-A32670

The Application of High Gradient Magnetic Separation in Nuclear Fuel Reprocessing

J. A. Williams, W. Baxter, G. Collins, K. Harding, C. M. Leslie, R. J. Sills

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 284-294

Technical Paper / Material / dx.doi.org/10.13182/NT81-A32671

Fission Track Annealing and Fission Track Age-Temperature Relationship in Sphene

T. D. Märk, M. Pahl, R. Vartanian

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 295-305

Technical Paper / Technique / dx.doi.org/10.13182/NT81-A32672

On the Minimum Overall Size of a Reflected Pebble-Bed Reactor

R. Chawla

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 306-309

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT81-A32673

An Empirical Equation for Estimating Nitric-Acid Extraction by Tri-n-Buytl Phosphate from Nitric Acid and Nitric-Acid/Sodium-Nitrate Solutions

J. C. Mailen

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 310-312

Technical Note / Chemical Processing / dx.doi.org/10.13182/NT81-A32674

Calculation of Neutron Die-Away Times in a Large-Vehicle Portal Monitor

R. A. Lillie, R. T. Santoro, R. G. Alsmiller, Jr.

Nuclear Technology / Volume 52 / Number 2 / February 1981 / Pages 313-318

Technical Note / Analysis / dx.doi.org/10.13182/NT81-A32675

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