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Volume 32

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Number 1

Materials Considerations in Radioactive Waste Storage

Warren K. Eister

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 6-9

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31731

Hanford Waste Encapsulation: Strontium and Cesium

R. R. Jackson

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 10-15

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31732

Stabilization and Storage of Solidified High-Level Radioactive Wastes

J. R. Berreth, A. P. Hoskins, J. A. Rindfleisch

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 16-24

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31733

Packaging Rocky Flats Waste

Charles E. Wickland

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 25-29

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31734

Some Techniques for the Solidification of Radioactive Wastes in Concrete

Peter Colombo, Robert M. Neilson, Jr.

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 30-38

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31735

Leach Behavior of Hydrofracture Grout Incorporating Radioactive Wastes

J. G. Moore, H. W. Godbee, A. H. Kibbey

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 39-52

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31736

Packaging of Tritium-Contaminated Liquid Waste

E. A. Mershad, W. W. Thomasson, J. J. Dauby

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 53-59

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31737

The Canadian Spent Fuel Storage Canister: Some Materials Aspects

Derek G. Boase, Tjalle T. Vandergraaf

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 60-71

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31738

High-Level Waste Glass

John E. Mendel

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 72-87

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31739

High-Level Waste Glass: Field Leach Test

W. F. Merritt

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 88-91

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31740

High-Level Waste Ceramics: Materials Considerations, Process Simulation, and Product Characterization

Gregory J. McCarthy

Nuclear Technology / Volume 32 / Number 1 / January 1977 / Pages 92-105

Technical Paper / Materials in Waste Storage / Radioactive Waste / dx.doi.org/10.13182/NT77-A31741

Number 2

In Situ Regeneration of Fusion Reactor First Walls

J. Chin, T. Ohkawa

Nuclear Technology / Volume 32 / Number 2 / February 1977 / Pages 115-124

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31717

Analysis of Reactor Component Fluence Limits Using Damage Function Methods

G. R. Odette, R. L. Simons, W. N. McElroy, D. G. Doran

Nuclear Technology / Volume 32 / Number 2 / February 1977 / Pages 125-141

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31718

Toroidal Field Strength Requirements in Tokamak Reactors

W. M. Stacey, Jr., K. Evans, Jr.

Nuclear Technology / Volume 32 / Number 2 / February 1977 / Pages 142-154

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31719

Sensitivity Assessments in Reactor Safety Analysis

J. E. Kelly, F. L. Leverenz, Jr., N. J. McCormick, R. C. Erdmann

Nuclear Technology / Volume 32 / Number 2 / February 1977 / Pages 155-166

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31720

Study of the Dissolution of Refractory PuO2 in Nitric-Hydrofluoric Acid Dissolvents at 100°C

O. K. Tallent, J. C. Mailen

Nuclear Technology / Volume 32 / Number 2 / February 1977 / Pages 167-175

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31721

Uranium-236 in Light Water Reactor Spent Fuel Recycled to an Enriching Plant

A. de la Garza

Nuclear Technology / Volume 32 / Number 2 / February 1977 / Pages 176-185

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31722

The Reactivity Perturbation Assay of Irradiated Fuel Rods

L. Green, J. T. Kriese, M. Natelson

Nuclear Technology / Volume 32 / Number 2 / February 1977 / Pages 186-204

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31723

A Gamma-Ray Perimeter Security System

Donald A. Close

Nuclear Technology / Volume 32 / Number 2 / February 1977 / Pages 205-210

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT77-A31724

Number 3

  • Table of Contents
  • Authors(L. T. Fan, David F. Aldis, S. Nazaré, G. Ondracek, B. Schulz, D. Bittermann, J. Wehling, Dieter Sommer, B. J. Wrona, J. T. A. Roberts, T. M. Galvin, G. T. Higgins, Günter Hartmann, Hiroji Katsuta, Takahiro Ishigai, Kazuo Furukawa, J. T. Holmes, C. R. F. Smith, M. M. Osterhout, W. H. Olson, J. A. Grundl, V. Spiegel, C. M. Eisenhauer, H. T. Heaton II, D. M. Gilliam, J. Bigelow, Lucy Wu Person)

Optimal Synthesis of a Power Plant Cooling System

L. T. Fan, David F. Aldis

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 222-238

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31747

Properties of Light Water Reactor Core Melts

S. Nazaré, G. Ondracek, B. Schulz

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 239-246

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31748

Reliability Analysis of the Decay Heat Removal System of a 1000-MW(e) Gas-Cooled Fast Breeder Reactor

D. Bittermann, J. Wehling

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 247-256

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31749

Comparison of the Power Distribution in Uranium and Plutonium Fuel Elements in the KWO Core

Dieter Sommer

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 257-275

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31750

Mechanical Response of UO2 Subjected to Transient Heating

B. J. Wrona, J. T. A. Roberts, T. M. Galvin, G. T. Higgins

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 276-289

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31751

The Overall Probability of Detection in Connection with the Optimization of Safeguards Effort

Günter Hartmann

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 290-296

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31752

Equilibrium Pressure and Solubility of Hydrogen in Liquid Lithium

Hiroji Katsuta, Takahiro Ishigai, Kazuo Furukawa

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 297-303

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31753

Sodium Purification by Cold Trapping at the Experimental Breeder Reactor II

J. T. Holmes, C. R. F. Smith, M. M. Osterhout, W. H. Olson

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 304-314

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31754

A Californium-252 Fission Spectrum Irradiation Facility for Neutron Reaction Rate Measurements

J. A. Grundl, V. Spiegel, C. M. Eisenhauer, H. T. Heaton II, D. M. Gilliam, J. Bigelow

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 315-319

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT77-A31755

The Application of SPOOL-FIRE in Theoretical Analysis and Experimental Comparison

Lucy Wu Person

Nuclear Technology / Volume 32 / Number 3 / March 1977 / Pages 320-325

Technical Note / Reactor / dx.doi.org/10.13182/NT77-A31756