Home / Publications / Journals / Nuclear Technology / Volume 54 / Number 3

Volume 54

Number 3

Table of Contents
Authors(C. C. Lin, C. R. Pao, J. S. Wiley, W. R. DeHollander, J. Hadermann, J. Patry, Katsuro Takahashi, Yoshiaki Himeno, Nobutomo Takahashi, June Takahashi, Tatsuro Iguchi, J. H. McFadden, M. P. Paulsen, G. C. Gose, G. C. Gose, C. E. Peterson, N. L. Ellis, J. A. McClure, Joseph A. Naser, Bal Raj Sehgal, Lance J. Agee, James R. White, Charles E. Hendrix, V. K. Chexal, W. H. Layman, W. W. Brown, G. B. Caldwell, T. G. Broughton, N. G. Trikouros, L. C. Pwu, T. G. Broughton, Gregg B. Swindlehurst, Joseph A. Naser, E. Lin, Y. H. Cheng, J. K. Hsiue, H. J. Diamond, W. G. Lee, James T. Cronin, Bruce C. Slifer, D. P. Griggs, T. J. Honan, E. D. Hughes, M. P. Paulsen, L. J. Agee, Gian Piero Celata, Franco Vittorio Frazzoli)
Overview(Lance J. Agee)
Textbook of Nuclear Medicine: Clinical Applications(D. A. Bromley)
Engineering Economy: Analysis of Capital Expenditures(Daniel F. Hang)
Plasma Transport, Heating and MHD Theory(Chan K. Choi)
The (p,n) Reaction and the Nucleon-Nucleon Force(D. A. Bromley)
From X-Rays to Quarks—Modern Physicists and Their Discoveries(D. A. Bromley)
Remarks on the Plutonium-240 Induced Pre-Ignition Problem in a Nuclear Device(Walter Seifritz)
Reply to “Remarks on the Plutonium-240 Induced Pre-Ignition Problem in a Nuclear Device”(Sümer Şahin)

A Mathematical Model of Corrosion Product Transport in the Boiling Water Reactor Primary System

C. C. Lin, C. R. Pao, J. S. Wiley, W. R. DeHollander

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 253-265

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32770

Radionuclide Chain Transport Through Heterogeneous Media

J. Hadermann, J. Patry

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 266-277

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT81-A32771

Regeneration of a Large Cold Trap

Katsuro Takahashi, Yoshiaki Himeno, Nobutomo Takahashi, June Takahashi, Tatsuro Iguchi

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 278-285

Technical Paper / Material / dx.doi.org/10.13182/NT81-A32772

RETRAN Dynamic Slip Model

J. H. McFadden, M. P. Paulsen, G. C. Gose

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 287-297

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32774

A One-Dimensional Reactor Kinetics Model for RETRAN

G. C. Gose, C. E. Peterson, N. L. Ellis, J. A. McClure

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 298-310

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32775

Analysis of Pressurized Water Reactor Anticipated Transient Without Scram Transients with RETRAN-02

Joseph A. Naser, Bal Raj Sehgal, Lance J. Agee

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 311-321

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32776

Modeling Loss-of-Fluid Test Small-Break Experiments with RETRAN

James R. White, Charles E. Hendrix

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 322-331

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32777

A RETRAN Analysis of the Crystal River Unit 3 Incident of February 26, 1980

V. K. Chexal, W. H. Layman, W. W. Brown, G. B. Caldwell

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 332-341

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32778

RETRAN Pressurized Water Reactor Applications at General Public Utilities

T. G. Broughton, N. G. Trikouros

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 342-357

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32779

RETRAN Simulation of Three Mile Island Unit 2 Startup Overfeed Incident

L. C. Pwu, T. G. Broughton

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 358-363

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32780

Oconee RETRAN Model Comparisons with Plant Transient Data

Gregg B. Swindlehurst

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 364-372

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32781

RETRAN Analysis of the Peach Bottom Turbine Trip Tests

Joseph A. Naser

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 373-379

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32782

Analysis of Chinshan Unit 1 Full Load Rejection Transient Using RETRAN

E. Lin, Y. H. Cheng, J. K. Hsiue

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 380-384

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32783

RETRAN Simulation of Peach Bottom 2 Beginning of Cycle 5 Main Steam Relief Valve Discharge Test

H. J. Diamond, W. G. Lee

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 385-392

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32784

Simulation of a Simultaneous Closure of All Main Steam Isolation Valves Without Scram for a Boiling Water Reactor/4 Using RETRAN-01

James T. Cronin, Bruce C. Slifer

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 393-397

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32785

RETRAN Calculation of Loss of Feedwater Transients at Connecticut Yankee

D. P. Griggs, T. J. Honan

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 398-409

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32786

A Drift-Flux Model of Two-Phase Flow for RETRAN

E. D. Hughes, M. P. Paulsen, L. J. Agee

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 410-421

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32787

High Void Fraction Measurements in Full-Scale Heat Transfer Tests

Gian Piero Celata, Franco Vittorio Frazzoli

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 422-425

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32788