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Table of Contents

Pellet Power Ratio in a Pellet-Suspension Fission Core
D. R. Kingdon, A. A. Harms
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 1-8
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35307
Study on Reactivity Worth of Beryllium by (n,2n) and (γ,n) Reactions
Tsuyoshi Misawa, Seiji Shiroya, Keiji Kanda
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 9-18
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35308
Assessment of the Simulation Capability of RELAP5/MOD3 Compared with IIST Tests for Loss of the Residual Heat Removal System During Midloop Operation
Yuh-Ming Ferng, Chien-Hsiung Lee
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 19-33
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35309
A Model for Nonvolatile Fission Product Release During Reactor Accident Conditions
Brent J. Lewis, Bernard André, Gérard Ducros, Denis Maro
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 34-54
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35310
Passive Cooling System with Temperature Control for Reactor Containments
Charles W. Forsberg, James C. Conklin
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 55-65
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35311
RELAP5/MOD3 Simulation of the Station Blackout Experiment Conducted at the IIST Facility
Yuh-Ming Ferng, Tay-Jian Liu, Chien-Hsiung Lee
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 66-77
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35312
Boron-Nitride-Coated Nuclear Fuels
Güngör Gündüz, İbrahım Uslu, Hasan H. Durmazuçar
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 78-90
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35313
Improvements in Boiling Water Reactor Uranium Utilization and Operating Experience with Burnup Increase
Takaaki Mochida, Katsumasa Haikawa, Jun-Ichi Yamashita, Akira Nishimura, Yutaka Iwata, Shiroh Arai
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 91-107
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35314
An Approach for Evaluating Equilibrium and Rate Constants for the Reaction of Np(V) with Nitric Acid in the Purex Process Using Process Data
Shunji Homma, Mitsuhiro Takanashi, Jiro Koga, Shiro Matsumoto, Masaki Ozawa
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 108-114
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35315
Preliminary Performance Assessment of the Engineered Barriers for a Low- and Intermediate-Level Radioactive Waste Repository
Won-Jin Cho, Jae-Owan Lee, Pil-Soo Hahn, Kwan-Sik Chun
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 115-126
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35316
Heat Removal Characteristics of a Primary Containment Vessel External Spray
Yoshiyuki Kataoka, Tadashi Fujii, Michio Murase
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 127-135
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35317

Number 2

Table of Contents

Analytic Initialization of Nonequilibrium Iodine and Xenon Distributions for Core Transient Simulation
Jae Seung Song, Nam Zin Cho, Byung Ho Lee, Sung Quun Zee
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 137-145
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35295
A Formal Approach for Quantitative Treatment of Modeling Uncertainties in Safety Analysis
Kwang-Il Ahn, Young-Ho Jin
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 146-159
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35296
Investigation of System Responses of the Maanshan Nuclear Power Plant to the Loss of Residual Heat Removal During Midloop Operation Using a RELAP5/MOD3 Simulation
Yuh-Ming Ferng, Shau-Shei Ma
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 160-172
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35297
Core Performance of Fast Reactors for Actinide Recycling Using Metal, Nitride, and Oxide Fuels
Takeshi Yokoo, Akihiro Sasahara, Tadashi Inoue, Jungmin Kang, Atsuyuki Suzuki
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 173-179
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35298
The GC Computer Code for Flow Sheet Simulation of Pyrochemical Processing of Spent Nuclear Fuels
Rajesh K. Ahluwalia, Howard K. Geyer
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 180-195
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35299
Treatment of Simulated High-Level Radioactive Waste with Formic Acid: Bench-Scale Study on Hydrogen Evolution
Chia-Lin W. Hsu, James A. Ritter
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 196-207
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35300
Efficient Modeling of Reactive Transport Phenomena by a Multispecies Random Walk Coupled to Chemical Equilibrium
Wilfried Pfingsten
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 208-221
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35301
A Comparison of (Th,Pu)O₂ and UO₂ Fuels as Waste Forms for Direct Disposal
Peter Taylor, William H. Hocking,† Lawrence H. Johnson, Roderick J. McEachern, Sham Sunder
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 222-230
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35302
Development and Assessment of U.S. Nuclear Regulatory Commission Thermal-Hydraulic System Computer Codes
Louis M. Shotkin
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 231-244
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35303
Failure-Dependent Test, Repair, and Shutdown Strategies: Reducing the Impact of Common-Cause Failures
Stanislav P. Uryasev, Pranab K. Samanta
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 245-256
Technical Paper | Reactor Operation | doi.org/10.13182/NT96-A35304
Exposure Buildup Factors of UO₂ Using the Monte Carlo Method
Ahmet Bozkurt, Nicholas Tsoulfanidis
Nuclear Technology | Volume 116 | Number 2 | November 1996 | Pages 257-260
Technical Note | Radiation Protection | doi.org/10.13182/NT96-A35305

Number 3

Analysis of Ya-21u Thermionic Fuel Elements
Dmitry V. Paramonov, Mohamed S. El-Genk
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 261-269
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35282
Modeling of Thermophoretic Deposition of Aerosols in Nuclear Reactor Containments
Almir Fernandes, Sudarshan K. Loyalka
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 270-282
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35283
Light Water Reactor Aerosol Containment Experiment LA4 Simulated by JERICHO and AEROSOLS-B2 Codes
Roberto Passalacqua, Didier Tarabelli, Claude Renault
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 283-292
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35284
Measurement and Modeling of Iodine Volatility Above Irradiated Csl Solutions
Greg J. Evans
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 293-305
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35285
An Experimental Investigation of Natural Convection Heat Transfer Within Horizontal Spent-Fuel Assemblies
Robert E. Canaan, Dale E. Klein
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 306-318
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35286
Influence of NO_x and HNO₂ on Iodine Quantity in Spent-Fuel Solutions
Tsutomu Sakurai, Akira Takahashi, Niroh Ishikawa, Yoshihide Komaki, Mamoru Ohnuki
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 319-326
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35287
The Reaction of Tri-n-Butyl Phosphate with Nitrates
M. Lee Hyder
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 327-333
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35288
Identifying Organizational Deficiencies Through Root-Cause Analysis
Ram W. Tuli, George E. Apostolakis, Jya-Syin Wu
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 334-359
Technical Paper | Reactor Operation | doi.org/10.13182/NT96-A35289
Combined Use of Nitric and Formic Acids to Reduce Hydrogen Emissions During the Treatment of High-Level Radioactive Waste
Chia-Lin W. Hsu, James A. Ritter
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 360-365
Technical Note | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35290
Evaporation and Wet Oxidation of Steam Generator Cleaning Solutions
Philip N. Baldwin, Jr.
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 366-372
Technical Note | Material | doi.org/10.13182/NT96-A35291
Epithermal Neutron Beam Upgrade with a Fission Plate Converter at the Brookhaven Medical Research Reactor
Hungyuan B. Liu, Francis J. Patti
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 373-377
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35292

Volume 116

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