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Volume 70

Number 1

Table of Contents
Authors(Lance J. Agee, Jorge Arpa, Alan S. Fatemi, S. K. Mathavan, Bruce E. Schmitt, E. D. Hughes, K. R. Katsma, M. P. Paulsen, G. D. Miller, J. G. Refling, A. J. Roscioli, S. A. Somma, C. A. Kukielka, L. M. Olson, Ernest V. Moore, S. F. Deng, K. K. Chitkara, B. B. Chu, Adel Alapour, Robert A. Hommerson, Craig E. Peterson, V. K. (Bindi) Chexal, William H. Layman, Richard D. Hentzen, Garry C. Gose, Richard F. Farman, Charles E. Hendrix, Jason Chao, Yine-Ping Ting, Craig E. Peterson, V. K. (Bindi) Chexal, Talmage B. Clements, M. A. Alammar, Norman T. Simms, Vincent P. Manno, Michael W. Golay, Terry F. Rees, Jess M. Cleveland, Kenneth L. Nash)

RETRAN Overview

Lance J. Agee

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 7-16

Overview / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33658

RETRAN Applications in Pressurized Thermal Shock Analysis of Turkey Point Units 3 and 4

Jorge Arpa, Alan S. Fatemi, S. K. Mathavan

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 17-25

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33659

RETRAN Analysis of the Hanford N Reactor for a Loss of Feedwater

Bruce E. Schmitt

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 26-29

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33660

Semi-Implicit Solution Methods for the RETRAN Model Equations

E. D. Hughes, K. R. Katsma, M. P. Paulsen

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 30-41

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33661

Engineering Analysis Activities in Support of Susquehanna Unit 1 Startup Testing and Cycle 1 Operations

G. D. Miller, J. G. Refling, A. J. Roscioli, S. A. Somma, C. A. Kukielka, L. M. Olson

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 42-52

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33662

RETRAN Analysis of Boiling Water Reactor Accidents

Ernest V. Moore, S. F. Deng, K. K. Chitkara, B. B. Chu

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 53-63

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33663

Analysis of Hatch-2 Dual Recirculation Pump Trip Startup Test

Adel Alapour, Robert A. Hommerson

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 64-73

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33664

An Investigation of Decreasing Reactor Coolant Inventory as a Mechanism to Reduce Power During a Boiling Water Reactor Anticipated Transient Without Scram

Craig E. Peterson, V. K. (Bindi) Chexal, William H. Layman, Richard D. Hentzen, Garry C. Gose

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 74-83

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33665

RETRAN-02 Analysis of Loss-of-Fluid Test Experiments L9-3 and L9-4

Richard F. Farman, Charles E. Hendrix, Jason Chao

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 84-93

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33666

RETRAN Analysis of the San Onofre Unit 2 Turbine Trip from 100% Power

Yine-Ping Ting

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 94-103

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33667

Analysis of a Hot-Leg Small Break Loss-of-Coolant Accident in a Three-Loop Westinghouse Pressurized Water Reactor Plant

Craig E. Peterson, V. K. (Bindi) Chexal, Talmage B. Clements

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 104-110

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33668

Comparison of RETRAN and RELAP5 Models to Oyster Creek Loss of Feedwater Transient

M. A. Alammar

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 111-119

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33669

RETRAN-02 Comparison of Natural Circulation Flow Rates at Babcock & Wilcox 177-FA Plants

Norman T. Simms

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 120-123

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33670

Analytical Investigation of Postaccident Containment Atmospheric Stratification

Vincent P. Manno, Michael W. Golay

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 124-132

Technical Paper / Third International Retran Meeting / Nuclear Safety / dx.doi.org/10.13182/NT85-A33671

Leaching of Plutonium from a Radioactive Waste Glass by Eight Groundwaters from the Western United States

Terry F. Rees, Jess M. Cleveland, Kenneth L. Nash

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 133-140

Technical Paper / Third International Retran Meeting / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33672