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Home / Publications / Journals / Nuclear Technology / Volume 100 / Number 2

Volume 100

Number 2

Application of Statistical Combination of Uncertainties to the Three Mile Island Unit 1 Flux/Flow Reactor Trip Setpoint

Tae Y. Byoun, Ardesar A. Irani, John D. Luoma, Ronald E. Engel, Kenneth J. Doran, Govinda S. Srikantiah

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 152-161

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34738

A Nondiffusive Solution Method for RETRAN-03 Boiling Water Reactor Stability Analysis

Mark P. Paulsen, John G. Shatford, John L. Westacott, Lance J. Agee

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 162-173

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34739

Homogenization and Functionalization of One-Dimensional Cross Sections for RETRAN

James T. Cronin, Kord S. Smith

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 174-183

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34740

Transient Analysis of the MSIV-ATWS in a 1000-MW(thermal) BWR-4

Martin A. Zimmermann

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 184-192

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34741

Improved Pressurized Water Reactor Steamline Break Analysis Using RETRAN-02, ARROTTA, and VIPRE-02

Antonio F. Dias, Laurance D. Eisenhart, Diane M. Bell, Terry J. Garrett, Glenn J. Neises, Lance J. Agee

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 193-202

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34742

Analysis of Cofrentes Abnormal Plant Transients with RETRAN-02 and RETRAN-03

Pedro Mata, Pablo García Sedano, Juan Serra

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 203-215

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34743

VIPRE—A Reactor Core Thermal-Hydraulics Analysis Code for Utility Applications

Govinda S. Srikantiah

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 216-227

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34744

Validation of RETRAN-03 by Simulating a Peach Bottom Turbine Trip and Boiloff at the Full Integral Simulation Test Facility

John L. Westacott, Craig E. Peterson, Seung Oh

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 228-245

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34745

VIPRE-02—A Two-Fluid Thermal-Hydraulics Code for Reactor Core and Vessel Analysis: Mathematical Modeling and Solution Methods

Joseph M. Kelly, Charles W. Stewart, Judith M. Cuta

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 246-259

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34746

Applied Research in Critical Heat Flux

Jeffrey T. Dillingham, James H. Stuhmiller

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 260-270

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34747

 

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