ANS / Publications / Journals / Nuclear Technology

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT96-A35317

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT96-A35305

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT96-A35292