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Home / Publications / Journals / Nuclear Technology / Volume 50 / Number 3

Volume 50

Number 3

  • Table of Contents
  • Authors(S. K. Bhattacharyya, J. A. Morman, R. G. Bucher, D. M. Smith, W. R. Robinson, E. F. Bennett, A. Kenigsberg, D. Hasan, E. Elias, Richard Simms, Robert K. Lo, William F. Murphy, Alan B. Rothman, George S. Stanford, Carolyn D. Heising-Goodman, John F. Carew, David J. Diamond, Richard Simms, M. Schad, R. Farhadieh, W. H. Gunther, B. H. Erkkila, R. S. Marshall)
  • The Energy Source Book(L. B. Church)

The Effect of Accidental Steam Entry on Gas-Cooled Fast Reactor Integral Neutronics Parameters

S. K. Bhattacharyya, J. A. Morman, R. G. Bucher, D. M. Smith, W. R. Robinson, E. F. Bennett

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 197-218

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32524

Parametric Study of Radioactive Release from a Breached Containment

A. Kenigsberg, D. Hasan, E. Elias

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 219-224

Technical Paper / Reactor / dx.doi.org/10.13182/NT80-A32525

TREAT Test E8 Simulating a Liquid-Metal Fast Breeder Reactor $3/s Overpower Accident with Irradiated Fast Test Reactor Type Fuel

Richard Simms, Robert K. LO, William F. Murphy, Alan B. Rothman, George S. Stanford

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 225-241

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT80-A32526

An Evaluation of the Plutonium Denaturing Concept as an Effective Safeguards Method

Carolyn D. Heising-Goodman

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 242-251

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT80-A32527

Using Fuel Performance to Determine Operating Limit Uncertainty Allowance

John F. Carew, David J. Diamond

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 252-256

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32528

An Evaluation of Fuel Motion in Recent TREAT Experiments with Liquid-Metal Fast Breeder Reactor Fuel

Richard Simms

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 257-266

Technical Paper / Fuel / dx.doi.org/10.13182/NT80-A32529

To the Corrosion of Austenitic Steel in Sodium Loops

M. Schad

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 267-288

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32530

Application of a Sodium Austenitic Corrosion Model to a Fuel Rod

M. Schad

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 289-297

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32531

One-Dimensional Penetration of Molten UO2 into Substrate Limestone Concrete

R. Farhadieh, W. H. Gunther

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 298-306

Technical Paper / Material / dx.doi.org/10.13182/NT80-A32532

A Thermal Neutron Coincidence Counting System

B. H. Erkkila, R. S. Marshall

Nuclear Technology / Volume 50 / Number 3 / October 1980 / Pages 307-313

Technical Paper / Instrument / dx.doi.org/10.13182/NT80-A32533

 

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