American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 61 / Number 1

Volume 61

Number 1

The Effect of Coolant Orificing on the Core Performance of a Heterogeneous Liquid-Metal Fast Breeder Reactor

Mamoru Konomura, Yoshiaki Oka, Shigehiro An

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 7-16

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33138

An Emergency Measurement System for the Rapid Assessment of Environmental Exposure

Karl Heinemann, Ralf Hille, Kurt Jürgen Vogt

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 17-24

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33139

Simple Reactor Model Simulation of a LOFT ATWS Event

J. Louis Tylee

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 25-32

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33140

Evaluation of Volatile and Gaseous Fission Product Behavior in Water Reactor Fuel Under Normal and Severe Core Accident Conditions

Jeffrey Rest

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 33-48

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33141

A Modified Borresen Coarse-Mesh Computation for a Three-Dimensional Pressurized Water Reactor Benchmark Problem

Chang Hyo Kim, Samuel H. Levine

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 49-54

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT83-A33142

Development of a Process for the Co-Conversion of Pu-U Nitrate Mixed Solutions to Mixed-Oxide Powder Using a Microwave Heating Method

Masumichi Koizumi, Katsuyuki Ohtsuka, Hiroto Isagawa, Hideo Akiyama, Akio Todokoro

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 55-70

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33143

Mass Spectrometric Study of the Potential of Al2O3/SiO2 Additives for the Retention of Cesium in Coated Particles

K. Hilpert, R. Odoj, H. W. Nürnberg

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 71-77

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33144

An Automated Procedure for Selecting Boiling Water Reactor Refueling Policies Following Operational Problems or Changes

S. H. Yeh, Alice Y. Ying, J. Weisman

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 78-92

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33145

Decontamination of Radioactive Metal Surfaces by Plasma Arc Gouging

Osamu Kuriyama, Takao Koyama, Makoto Kikuchi

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 93-99

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33146

Effect of Helium Pressure on the Response of Unirradiated UO2 Subjected to Thermal Transients

G. R. Fenske, R. B. Poeppel, J. E. Emerson, P. M. Chapello, S. G. Das, R. H. Sevy

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 100-112

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33147

Temperature-Dependent Microhardness of A533-B Reactor Pressure Vessel Steels

Bryce L. Shriver, Thomas G. Hook

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 113-117

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33148

Investigations on the Improvement of the Iodine Filtration Concept of Pressurized Water Reactors

H. Deuber, J. G. Wilhelm

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 118-120

Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT83-A33149

A Liquid-Metal Fast Breeder Reactor Fueling Concept for Thorium Utilization and Improved Inherent Safety

Yuji Ishiguro

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 121-126

Technical Note / Fuel Cycle / dx.doi.org/10.13182/NT83-A33150

Method for the Sealing and Decontamination of Radioactive and Radioactively Contaminated Components and Materials

Daniel Neupert, Peter Demtröder

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 127-128

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33151