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Volume 52

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Number 1

Table of Contents
Authors(Kenji Yamazaki, Shigeharu Fujita, Toshimasa Kamata, Yoshitake Morikawa, Kunio Numata, Kenji Osamura, Yoshinori Meguro, Wayne R. Meier, Ronald W. King, Erwin C. Filewicz, S. J. Hakim, T. H. Bauer, R. O. McNary, Charles Abou-Ghantous, Leonard W. Gray, P. Werner, H. Blank, F. S. Gunnerson, D. T. Sparks, D. K. Kerwin, S. L. Sutter, J. W. Johnston, P. C. Owzarski, J. Mishima, L. C. Schwendiman, E. W. Becker, P. Nogueira Batista, H. Vlcker, F. J. Sandalla, Yakov Ben-Haim, Ezra Elias, Alexander Knoll, John W. Wilson, Govind S. Khandelwal, R. J. DiMelfia, James D. Wolcott, J. N. Anno)
Tritium in the Environment(Geoffrey G. Eichholz)
Proceedings of the Workshop on Low-Flow, Low-Permeability Measurements in Largely Impermeable Rocks(G. G. Eichholz)
Radiostrontium Movement in Soils and Uptake in Plants(Gregory R. Choppin)
“Criticality Experments with Subcritical Clusters of Low Enriched UO₂ Rods in Water with Uranium or Lead Reflecting Walls’”(S. R. Bierman, B. M. Durst, E. D. Clayton)
“Critical Experiments with Concrete-Reflected Fast Test Reactor Fuel Pins in Water,”(S. R. Bierman, B. M. Durst, E. D. Clayton, B. W. Howes)

Analysis on the Primary System Radiation Control at Tsuruga Boiling Water Reactor Plant

Kenji Yamazaki, Shigeharu Fujita, Toshimasa Kamata, Yoshitake Morikawa, Kunio Numata, Kenji Osamura, Yoshinori Meguro

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 7-21

Technical Paper / Reactor / dx.doi.org/10.13182/NT81-A32685

Two-Dimensional Neutronics Calculation for the High Yield Lithium Injection Fusion Energy Converter

Wayne R. Meier

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 22-31

Technical Paper / Reactor / dx.doi.org/10.13182/NT81-A32686

Retrieval of Damaged Subassembly from Experimental Breeder Reactor II Primary Tank

Ronald W. King, Erwin C. Filewicz

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 32-42

Technical Paper / Reactor / dx.doi.org/10.13182/NT81-A32687

An Analysis of the Thermal Behavior of a Stagnant Pool for Fast Reactor Safety

S. J. Hakim, T. H. Bauer, R. O. McNary

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 43-56

Technical Paper / Reactor / dx.doi.org/10.13182/NT81-A32688

An Economic Model for Fuel Cycle Cost

Charles Abou-Ghantous

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 57-65

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT81-A32689

Rapid Dissolution of Plutonium Metal in Sulfamic Acid Followed by Conversion to a Nitric Acid Medium

Leonard W. Gray

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 66-72

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT81-A32690

Mechanical Properties of Advanced Fuels Under Compressive Deformation

P. Werner, H. Blank

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 73-85

Technical Paper / Fuel / dx.doi.org/10.13182/NT81-A32691

Film Boiling Behavior of a Pressurized Water Reactor Type Fuel Bundle

F. S. Gunnerson, D. T. Sparks, D. K. Kerwin

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 86-99

Technical Paper / Fuel / dx.doi.org/10.13182/NT81-A32692

Depleted Uranium Dioxide Powder Flow Through Very Small Openings

S. L. Sutter, J. W. Johnston, P. C. Owzarski, J. Mishima, L. C. Schwendiman

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 100-104

Technical Paper / Fuel / dx.doi.org/10.13182/NT81-A32693

Uranium Enrichment by the Separation Nozzle Method Within the Framework of German/Brazilian Cooperation

E. W. Becker, P. Nogueira Batista, H. Vlcker

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 105-114

Technical Paper / Isotopes Separation / dx.doi.org/10.13182/NT81-A32694

Measurement of Sulfur-35 in the Coolant Gas of the Windscale Advanced Gas-Cooled Reactor

F. J. Sandalls

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 115-120

Technical Paper / Analysis / dx.doi.org/10.13182/NT81-A32695

Nondestructive Analysis of Radwaste Containers

Yakov Ben-Haim, Ezra Elias, Alexander Knoll

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 121-128

Technical Paper / Technique / dx.doi.org/10.13182/NT81-A32696

Response of Large Cavity Ion Chambers to Space Protons

John W. Wilson, Govind S. Khandelwal

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 129-133

Technical Paper / Technique / dx.doi.org/10.13182/NT81-A32697

A Note on Transient Fuel Behavior Maps for Oxide Nuclear Reactor Fuel

R. J. DiMelfi

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 134-138

Technical Note / Fuel / dx.doi.org/10.13182/NT81-A32698

Gamma-Induced Electron Emission from Conducting Surfaces

James D. Wolcott, J. N. Anno

Nuclear Technology / Volume 52 / Number 1 / January 1981 / Pages 139-140

Technical Note / Radiation / dx.doi.org/10.13182/NT81-A32699

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

Number 3

Table of Contents
Authors(Richard Simms, Gerald E. Marsh, Alan B. Rothman, George S. Stanford, S. R. Bierman, E. D. Clayton, Samuel H. Levine, Mortimer A. Schultz, Daren Chang, C. O. Slater, S. N. Cramer, D. T. Ingersoll, M. L. Williams, F. J. Muckenthaler, J. J. Manning, J. L. Hull, S. F. Su, Y. Orechwa, H. Henryson II, David A. Mandell, E. D. Jones, A. McBride, K. C. Thomas, M. A. Hassan, K. Rehme, P. A. Tempest, Morris Schwarzblat, M. E. Anderson, L. V. Hampton, G. J. Licina, P. Roy, A. R. Shepherd, J. N. Anno, Woon H. Chung, J. N. Anno)
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 “Comments on ‘The Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input’”(D. H. Nguyen)
Annual Review of Nuclear and Particle Science: Volume 28(Paul F. Zweifel)
Nuclear Power and Its Environmental Effects(Carolyn Heising-Goodman)
Formation of Uranium Ore Deposits(Arthur L. Reesman)
Status and Prospects of Thermal Breeders and Their Effect on Fuel Utilization(Kazys K. Almenas)
Short Course in Uranium Deposits: Their Mineralogy and Origin(Arthur L. Reesman)

Loss-of-Flow Transient Reactor Test Facility Tests L6 and L7 with Irradiated Liquid-Metal Fast Breeder Reactor Type Fuel

Richard Simms, Gerald E. Marsh, Alan B. Rothman, George S. Stanford

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 331-341

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32707

Criticality Experiments with Subcritical Clusters of Light Water Reactor Type Fuel Separated by a Flux Trap

S. R. Bierman, E. D. Clayton

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 342-346

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32708

A Method of Performing Shutdown Reactivity Measurements in Spent Nuclear Fuel Storage Pools

Samuel H. Levine, Mortimer A. Schultz, Daren Chang

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 347-353

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32709

Measurement and Calculation of the Effectiveness of the Gas-Cooled Fast Breeder Reactor Grid-Plate Shield

C. O. Slater, S. N. Cramer, D. T. Ingersoll, M. L. Williams, F. J. Muckenthaler, J. J. Manning, J. L. Hull

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 354-369

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32710

Neutronic Space-Time Effects with Thermal-Hydraulic Feedback in Large Homogeneous and Heterogeneous Liquid-Metal Fast Breeder Reactors

S. F. Su, Y. Orechwa, H. Henryson II

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 370-382

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32711

Geometrical View Factors for Radiative Heat Transfer Within Boiling Water Reactor Fuel Bundles

David A. Mandell

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 383-392

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32712

The Fabrication of Grid Spacer Assemblies for Liquid-Metal Fast Breeder Reactors

E. D. Jones, A. McBride, K. C. Thomas

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 393-400

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32713

Heat Transfer near Spacer Grids in Gas-Cooled Rod Bundles

M. A. Hassan, K. Rehme

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 401-414

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT81-A32714

A Comparison of Borosilicate Glass and Synthetic Minerals as Media for the Immobilization of High-Level Radioactive Waste

P. A. Tempest

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 415-425

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT81-A32715

An Equation-of-State of Xenon for Nonequilibrium Bubble Kinetics Calculations During Fast Transients

Morris Schwarzblat

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 426-427

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT81-A32716

Increases in Neutron Yield of ²³⁹Pu-Be(α,n) Sources—II

M. E. Anderson

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 428-430

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT81-A32717

Waterside Corrosion Correlations for Cr—1 Mo Steel in Liquid-Metal Fast Breeder Reactor Steam Generators

L. V. Hampton, G. J. Licina, P. Roy

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 431-434

Technical Note / Material / dx.doi.org/10.13182/NT81-A32718

Radiation-Induced Outgassing from Several Metals

A. R. Shepherd, J. N. Anno

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 435-436

Technical Note / Material / dx.doi.org/10.13182/NT81-A32719

Radiation-Induced Gas Evolution from Several Organic Liquids

Woon H. Chung, J. N. Anno

Nuclear Technology / Volume 52 / Number 3 / March 1981 / Pages 437-438

Technical Note / Material / dx.doi.org/10.13182/NT81-A32720