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Home / Publications / Journals / Nuclear Technology / Volume 93 / Number 1

Volume 93

Number 1

Application of RETRAN-02 to Plant Transient Analysis and Issue Resolution

Pedro Mata Alonso, Rafael Otero Carrasco, Pablo Garcia Sedano

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 7-15

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34513

Developing RETRAN Input for Redundant Networks

Kenneth J. Doran, Ronald E. Engel, Randall S. May

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 16-21

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34514

Steam Line Break Analysis Comparison to the Wolf Creek Updated Safety Analysis Report

Glenn J. Neises, Terry J. Garrett

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 22-35

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34515

Core Boiling During Midloop Operation

Nobuyuki Fujita, David A. Rice

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 36-46

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34516

A Survey of the Oyster Creek Reload Licensing Model

Mansur A. Alammar

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 47-52

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34517

Palo Verde Nuclear Generating Station Midloop Condition RETRAN Model

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 53-64

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34518

Response Surface Development Using RETRAN

Ronald E. Engel, John M. Sorensen, Randall S. May, Kenneth J. DOran, N. G. Trikouros, Eugene S. Mozias

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 65-81

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34519

Analysis of a Neutron Flux Oscillation Event at LaSalle-2

Fumimasa Araya, Kazuo Yoshida, Masashi Hirano, Yukihisa Yabushita

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 82-91

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34520

Consistent Initialization of Pressure and Flow Parameters for BWR Transient Analysis at Off-Rated Power and Flow Conditions

Bennett J. Gitnick

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 92-104

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34521

The RETRAN-03 Computer Code

M. P. Paulsen, J. H. McFadden, C. E. Peterson, J. A. McClure, G. C. Gose, P. J. Jensen

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 105-115

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34522

Compiler Issues Associated with Safety-Related Software

Lynn R. Feinauer

Nuclear Technology / Volume 93 / Number 1 / January 1991 / Pages 116-122

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34523

 

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