American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 59 / Number 1

Volume 59

Number 1

Tritium Analysis of Irradiated Burnable Poison Rods

Filippo D’Annucci, Elma Beth S. Pardue, Wilfried Rommelaere, Günter Bäro

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 9-13

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A33048

Reduced Temperature Return-to-Power Demonstration

C. E. Meyer, N. P. Mueller, M. Plumier, M. G. Watts, R. Leroy, C. J. Saint-Mard

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 14-19

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A33049

The German Risk Study: Accident Consequence Model and Results of the Study

Anton Bayer, Klaus Burkart, Joachim Ehrhardt, Wolfgang Hübschmann, Manfred Schückler, Siegfried Vogt, Wolfgang Jacobi, Herwig G. Paretzke, Klaus-Rüdiger Trott, Eduard Hofer, Bernard Krzykacz

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 20-50

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A33050

An Alternative Solvent Cleanup Method Using a Hydrazine Oxalate Wash Reagent

O. K. Tallent, James C. Mailen

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 51-62

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT82-A33051

Determination of Thermal Accommodation Coefficients of Inert Gases on a Surface of Vitreous UO2 at ∼35°C

Lloyd B. Thomas, Sudarshan K. Loyalka

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 63-69

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A33052

Behavior of (U,Pu)O2 Sphere-Pac Fuel, with Plutonium in the Large Spheres Only, in Low Burnup Tests Under Pressurized Water Reactor Conditions

Aart Van Der Linde, Jacques H. N. Verheugen

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 70-77

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A33053

Some Preliminary Waste Management Considerations for Ground Processing Systems Supporting the Space Option

D. William Tedder

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 78-84

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A33054

Evaluation of an International, Perpetual, and Retrievable Facility for Storage of Vitrified Radioactive Waste

Leona Marshall Libby, M. G. Wurtele, Chris G. Whipple

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 85-98

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A33055

Fundamental Underwater Cutting Method Experiment as a Dismantling Tool for a Commercial Atomic Reactor Vessel

Masanobu Hamasaki, Yasuichi Murao, Fumikazu Tateiwa

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 99-103

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A33056

Rapid Estimation of the Regional Thermal Response to a Nuclear Waste Repository—Limiting Case Analysis

Christopher J. Blesch, F. A. Kulacki, R. N. Christensen

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 104-118

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A33057

Regional Waste Treatment Facilities with Underground Monolith Disposal for All Low-Heat-Generating Nuclear Wastes

Charles W. Forsberg

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 119-135

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT82-A33058

Fatigue Crack Growth Curve in Air Environment at 300°C for Stainless Steels

Jean-Louis Bernard, Georges S. Slama

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 136-147

Technical Paper / Material / dx.doi.org/10.13182/NT82-A33059

Distributions of Velocity and Turbulence in a Parallel Flow Along an Asymmetric Rod Bundle

Klaus Rehme

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 148-159

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT82-A33060

Enhancement of Heat Transfer Between Two Horizontal Liquid Layers by Gas Injection at the Bottom

Heinrich Werle

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 160-164

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT82-A33061

Design and Testing of an Electrochemical Carbon Meter for Sodium

Thiagarajan Gnanasekaran, Hans U. Borgstedt, Günther Frees

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 165-169

Technical Paper / Technique / dx.doi.org/10.13182/NT82-A33062

OPTO: Optimization Program for Multicomponent Activation Detectors

P. A. Aarnio, M. J. Koskelo+

Nuclear Technology / Volume 59 / Number 1 / October 1982 / Pages 170-185

Technical Paper / Technique / dx.doi.org/10.13182/NT82-A33063