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Number 1

Table of Contents
Overview of 1988–1989 RETRAN Activity (Lance J. Agee)

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT91-A34523

Number 2

Table of Contents
Laser Science & Technology (N. V. V. J. Swamy)

Sensitivity Analysis of Thermal-Hydraulic Parameters and Probability Estimation of Boiling Transition in a Standard BWR/6
Smaeil M. Aceil, Doyle R. Edwards
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 123-130
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34498
Sequential Probability Ratio Test for Nuclear Plant Component Surveillance
Kenny C. Gross, Keith E. Humenik
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 131-137
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34499
Core Simulations Using Actual Detector Readings for a Canada Deuterium Uranium Reactor
Bong Ghi Kim, In Sup Kim, Seong Yun Kim
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 138-146
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34500
Decontamination of Liquid-Metal Fast Breeder Reactor Components for Reuse: The French Experience
Patrick Michaille, Jean-Claude Moroni, Irma Lambert
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 147-157
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34501
The Potential for Catastrophic Fuel Damage During Beyond-Design-Basis Overpressurization Accidents in a Boiling Water Reactor
David J. Diamond, Dragan Mirkovic, Chia-Jung Hsu, Robert Fitzpatrick
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 158-165
Technical Paper | Nuclear Reactor Safet | doi.org/10.13182/NT91-A34502
Countercurrent Flow Limitation Model for RELAP5/MOD3
Richard A. Riemke
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 166-173
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34503
Small-Scale Experiments Conducted to Support Investigation of HypotheticalDesign-Basis LOCA Phenomena in the Advanced Test Reactor
Thomas K. Larson, Keith G. Condie, Steven T. Polkinghorne, Brent J. Buescher
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 174-194
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34504
A Statistical Model for Prediction of Fuel Element Failure Using the Markov Process and Entropy Minimax Principles
Kie-Yong Choi, Young-Ku Yoon, Soon-Heung Chang
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 195-205
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT91-A34505
Development of Partitioning and Transmutation Technology for Long-Lived Nuclides
Tadashi Inoue, Masahiro Sakata, Hajime Miyashiro, Tetsuo Matsumura, Akihiro Sasahara, Nobuya Yoshiki
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 206-220
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34506
Severe Accident Zircaloy Oxidation/Hydrogen Generation Behavior Noted from In-Pile Test Data
August W. Cronenberg
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 221-239
Technical Paper | Material/Nuclear Safety | doi.org/10.13182/NT91-A34507
RELAP5 Simulation of Advanced Test Reactor Scaled LOCA Experiments 7, 8, 12, and 14
Steven T. Polkinghorne, Thomas K. Larson, Brent J. Buescher
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 240-251
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34508
Development of a Computer Code to Simulate Aerosol Behavior in a Vented Containment
A. K. Ahluwalia, A. M. C. Chan
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 252-259
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34509

Number 3

Table of Contents
Radioactive Waste Management (Nicholas Tsoulfanidis, Robert G. Cochran)

A High-Breeding Fast Reactor with Fission Product Gas Purge/Tube-in-Shell Metallic Fuel Assemblies
Toru Hiraoka, Kiyoshi Sako, Hideki Takano, Takeshi Ishii, Mitsuru Sato
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 305-329
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34526
Reactor Design of the Advanced Neutron Source
John M. Ryskamp, Douglas L. Selby, R. Trenton Primm III
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 330-349
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34527
Control Room Habitability During Severe Accidents
Raymond P. Siu
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 350-356
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34528
Studies of Neutron Shielding Properties of Ilmenite-Magnetite Concrete Using A ²⁵²Cf Source
S. I. Bhuiyan, F. U. Ahmed, A. S. Mollah, M. A. Rahman
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 357-361
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34529
Numerical Study of Hydrodynamics in Pulsed Solvent Extraction Columns Using the Dynac Code
Masahiro Nabeshima
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 362-374
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT91-A34530
Purex Processing of 10-Year Light Water Reactor Fuel: Flow Sheet
Okan H. Zabunoglu, Bernard I. Spinrad
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 376-381
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT91-A34531
A Method to Evaluate the Maximum Allowable Temperature of Spent Fuel in Dry Storage During a Postulated Accident
Masami Mayuzumi, Takeo Onchi
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 382-388
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT91-A34532
Flux and Fluence Determination Using the Material Scrapings Approach
Michael P. Manahan, Sr., Hassan S. Basha
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 389-398
Technical Paper | Material | doi.org/10.13182/NT91-A34533
High-Temperature Corrosion Testing of Alumina and Zirconia in Uranium Hexafluoride Environment
Simon C. P. Wang, Clayton Collins, Samim Anghaie, E. Dow Whitney
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 399-411
Technical Paper | Material | doi.org/10.13182/NT91-A34534
A Step-Heating Dilatometry Method to Measure the Change in Length Due to Annealing of a SiC Temperature Monitor
Toyohiko Yano, Kazunari Sasaki, Tadashi Maruyama, Takayoshi Iseki, Masahiko Ito, Shoji Onose
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 412-415
Technical Note | Material | doi.org/10.13182/NT91-A34535

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