ANS / Publications / Journals / Nuclear Technology

Accelerator-Driven Subcritical Target Concept for Transmutation of Nuclear Wastes

Gregory J. Van Tuyle, Michael Todosow, Marcia J. Geiger, Arnold L. Aronson, H. Takahashi

Nuclear Technology / Volume 101 / Number 1 / January 1993 / Pages 1-17

Technical Paper / Waste Management Special / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34764

Risk, Uncertainty in Risk, and the EPA Release Limits for Radioactive Waste Disposal

Jon C. Helton

Nuclear Technology / Volume 101 / Number 1 / January 1993 / Pages 18-39

Technical Paper / Waste Management Special / Radioactive Waste Disposal / dx.doi.org/10.13182/NT93-A34765

An Ocean Island Geological Repository—A Second-Generation Option for Disposal of Spent Fuel and High-Level Waste

Charles W. Forsberg

Nuclear Technology / Volume 101 / Number 1 / January 1993 / Pages 40-53

Technical Paper / Waste Management Special / Radioactive Waste Disposal / dx.doi.org/10.13182/NT93-A34766

A Numerical Study of Transient Mass Transport Through a Circular Hole Connecting Two Semi-Infinite Media

David W. DePaoli, Timothy C. Scott

Nuclear Technology / Volume 101 / Number 1 / January 1993 / Pages 54-66

Technical Paper / Waste Management Special / Radioactive Waste Disposal / dx.doi.org/10.13182/NT93-A34767

An Analytical Model for Radionuclide Transport in a Single Fracture: Considering Nonequilibrium Matrix Sorption

Ching-Hor Lee, Shi-Ping Teng

Nuclear Technology / Volume 101 / Number 1 / January 1993 / Pages 67-78

Technical Paper / Waste Management Special / Radioactive Waste Disposal / dx.doi.org/10.13182/NT93-A34768

Diffusion of the ²⁴¹Am → ²³⁷Np Decay Chain Limited by Their Elemental Solubilities in the Artificial Barriers of High-Level Radioactive Waste Repositories

Joonhong Ahn, Atsuyuki Suzuki

Nuclear Technology / Volume 101 / Number 1 / January 1993 / Pages 79-91

Technical Paper / Waste Management Special / Radioactive Waste Disposal / dx.doi.org/10.13182/NT93-A34769

Migration of Radionuclides in Fractured Porous Rock: Analytical Solution for a Flux-Type Boundary Condition

Shean-Lang Chiou, Shih-Hai Li

Nuclear Technology / Volume 101 / Number 1 / January 1993 / Pages 92-100

Technical Paper / Waste Management Special / Radioactive Waste Disposal / dx.doi.org/10.13182/NT93-A34770

A Methodology for the Design and Analysis of a Sensor Failure Detection Network

H. P. Chou, J. N. Ning, T. M. Tsai

Nuclear Technology / Volume 101 / Number 1 / January 1993 / Pages 101-109

Technical Note / Waste Management Special / Reactor Operation / dx.doi.org/10.13182/NT93-A34771

Neural Network Model for Estimating Departure from Nucleate Boiling Performance of a Pressurized Water Reactor Core

Hyun-Koon Kim, Seung-Hyuk Lee, Soon-Heung Chang

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 111-122

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34773

Radis—a Regional Nuclear Accident Consequence Analysis Model for Hong Kong

Mankit Ray Yeung, Eric M. K. Ching

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 123-139

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34774

A Comparative Study of Nuclear Accident Consequences for Hong Kong

Eric M. K. Ching, Mankit Ray Yeung

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 140-148

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34775

A Probabilistic Safety Criterion for Core Melt Frequency Based on the Distribution of the Public’s Safety Goals

Ki-Yong Ra, Byong-Whi Lee, Soon-Heung Chang

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 149-158

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34776

Abnormal Event Identification in Nuclear Power Plants Using a Neural Network and Knowledge Processing

Yukiharu Ohga, Hiroshi Seki

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 159-167

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34777

The Use of Nonlinear Regression Analysis for Integrating Pollutant Concentration Measurements with Atmospheric Dispersion Modeling for Source Term Estimation

Leslie L. Edwards, Robert P. Freis, Linda G. Peters, Paul H. Gudiksen, Sergei E. Pitovranov

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 168-180

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34778

RELAP5 Modeling of the Westinghouse Model D4 Steam Generator

Borut Mavko, Stojan Petelin, Oton Gortnar

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 181-192

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34779

Some Aspects of Nuclear Power Plant Safety Under War Conditions

Andrej Stritar, Borut Mavko, Janez Sušnik, Božidar Šarler

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 193-201

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34780

A Power-Rate-Dependent Model for Pellet/Cladding Mechanical Interaction

Chlng-Kong Chao, Che-Chung Tseng

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 202-211

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34781

An Application of the Concept of Limit of Expenditures in Risk Reduction Measures to the Brazilian Case

L. F. Oliveira, J. E. Lima, P. F. Frutuoso E Melo

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 212-217

Technical Paper / Economic / dx.doi.org/10.13182/NT93-A34782

Fire Behavior and Filter Plugging During a Postulated Solvent Fire in the Extraction Process of a Nuclear Fuel Reprocessing Plant

Kazuichiro Hashimoto, Gunji Nishio, Kunihisa Soda

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 218-226

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34783

A Two-Fluid Two-Phase Model for Thermal-Hydraulic Analysis of a U-Tube Steam Generator

Huan-Jen Hung, Ching-Chang Chieng, Bau-Shei Pei, Song-Feng Wang

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 227-236

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A34784

Transport Analysis of Several Cross-Section Libraries Used for Reactor Pressure Vessel Fluence Calculations

Alireza Haghighat, Ramana Veerasingam

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 237-243

Technical Note / Material / dx.doi.org/10.13182/NT93-A34785

RELAP5/MOD3 Simulation of the Water Cannon Phenomenon

W. S. Yeung, Jen Wu, R. T. Fernandez, R. K. Sundaram

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 244-251

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A34786

Results of Recent Investigations at Sandia National Laboratories on Core Debris Interactions with Concrete

Dana A. Powers, Ervin R. Copus, David R. Bradley

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 255-261

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34788

Fission Product Transport Behavior

T. S. Kress, E. C. Beahm, C. F. Weber, G. W. Parker

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 262-269

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34789

Fission Product Release from Fuel Under Severe Accident Conditions

Richard R. Hobbins, David A. Petti, Donald L. Hagrman

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 270-281

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34790

Recent Advances in Severe Accident Technology — Direct Containment Heating in Advanced Light Water Reactors

Mario H. Fontana

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 282-298

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34791

The Probability of Liner Failure in a Mark-I Containment, Part I: Probabilistic Framework and Results

Theo G. Theofanous, Hongfei Yan, Farouk Eltawila

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 299-331

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34792

The Probability of Liner Failure in a Mark-I Containment, Part II: Melt Release and Spreading Phenomena

Theo G. Theofanous, Hongfei Yan

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 332-353

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34793

The Probability of Liner Failure in a Mark-I Containment, Part III: Corium/Concrete Interactions and Liner Attack Phenomena

W. H. Amarasooriya, Hongfei Yan, Umesh Ratnam,†, Theo G. Theofanous

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 354-384

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34794

Cooling of Core Debris Within the Reactor Vessel Lower Head

Robert E. Henry, James P. Burelbach, Robert J. Hammersley, Christopher E. Henry, George T. Klopp

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 385-399

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34795

Hydrogen Production and Combustion in Severe Reactor Accidents: An Integral Assessment Perspective

Martin G. Plys

Nuclear Technology / Volume 101 / Number 3 / March 1993 / Pages 400-410

Technical Paper / Severe Accident Technology / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34796