ANS / Publications / Journals / Nuclear Technology

Integration of Neural Networks with Fuzzy Reasoning for Measuring Operational Parameters in a Nuclear Reactor

Andreas Ikonomopoulos, Lefteri H. Tsoukalas, Robert E. Uhrig

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 1-12

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34866

Sensitivity and Uncertainty Analysis of Accident Management Strategies Involving Multiple Decisions

Moosung Jae, Antony D. Milici, William E. Kastenberg, George E. Apostolakis

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 13-36

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34867

Constituent Migration Model for U-Pu-Zr Metallic Fast Reactor Fuel

Masayoshi Ishida, Takanari Ogata, Motoyasu Kinoshita

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 37-51

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34868

Postirradiation Recovery of a Reactor Pressure Vessel Steel Investigated by Positron Annihilation and Microhardness Measurements

Ramiro Pareja, Nieves De Diego, Rosa Maria De La Cruz, Javier Del Río

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 52-63

Technical Paper / Material / dx.doi.org/10.13182/NT93-A34869

A New Flooding Correlation Development and Its Critical Heat Flux Predictions Under Low Air-Water Flow Conditions in Savannah River Site Assembly Channels

Si Y. Lee

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 64-75

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A34870

Analysis of Experiments for Steam Condensation in the Presence of Non-condensable Gases Using the RELAP5/MOD3 Code

Yassin A. Hassan, Laxminarayan L. Raja

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 76-88

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A34871

Ventilation Rates by Measurement of Induced Radon Time-Dependent Behavior—Theory, Application, and Evaluation

Bobby E. Leonard

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 89-105

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT93-A34872

Development of an In-Service Inspection Technique for the Intermediate Heat Exchanger Tubes of the High-Temperature Engineering Test Reactor

Yoshiyuki Inagaki, Yoshiaki Miyamoto, Tamao Nakajima, Tsuyoshi Kozuma, Hajime Shoji

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 106-117

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A34873

An Assessment of Liquid-Metal Centrifugal Pumps at Three Fast Reactors

Mark S. Smith, Darren H. Wood, James D. Drischler

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 118-127

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A34874

Detection of Small Leakages by a Combination of Dedicated Kalman Filters and an Extended Version of the Binary Sequential Probability Ratio Test

Attila Rácz

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 128-146

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT93-A34875

Control System Modification in the Taiwan Research Reactor

Shih-Jen Wang, Min-Song Lin

Nuclear Technology / Volume 104 / Number 1 / October 1993 / Pages 147-153

Technical Note / Reactor Operation / dx.doi.org/10.13182/NT93-A34876

Validation of the TEXSAN Thermal-Hydraulic Analysis Program

Shawn P. Burns, Dale E. Klein

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 157-163

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34879

The Influence of Moisture on Air Oxidation of UO₂: Calculations and Observations

Peter Taylor, Robert J. Lemire, Donald D. Wood

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 164-170

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34880

An Evaluation of the Use of Depleted Uranium as a Structural Component for Transport Casks

Paul McConnell, Richard Salzbrenner, Gerald W. Wellman, Ken B. Sorenson

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 171-181

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34881

Demands Placed on Waste Package Performance Testing and Modeling by Some General Results of Reliability Analysis

Dwayne A. Chesnut

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 182-192

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34882

Long-Term Comparison of Dissolution Behavior Between Fully Radioactive and Simulated Nuclear Waste Glasses

Xiangdong Feng, John K. Bates, Edgar C. Buck, Charles R. Bradley, Meiling Gong

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 193-206

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34883

Criticality Safety of Transuranic Storage Arrays at the Waste Isolation Pilot Plant

William A. Boyd, Mark W. Fecteau

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 207-218

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34884

Multibarrier Copper-Base Containers for High-Level Waste Disposal

Dale T. Peters, Konrad J. A. Kundig, David F. Medley, Paul A. Enders

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 219-232

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34885

Attainment of Radiation Equivalency in Nuclear Power Radioactive Product Management

E. O. Adamov, I. Kh. Ganev, V. V. Orlov

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 233-240

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34886

Combined Natural Convection and Surface Radiation in the Annular Region Between a Volumetrically Heated Inner Tube and a Finite Conducting Outer Tube

Steven Gianoulakis, Dale E. Klein

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 241-251

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34887

Geochemical Modeling of a Bentonite-Groundwater-Rock System in the Presence of Uranium

Iréne Lundén, Karin Andersson

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 252-257

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34888

Radionuclide Migration in Fractured Porous Rock: Analytical Solution for a Kinetic Solubility-Limited Dissolution Model

Shih-Hai Li, Shean-Lang Chiou

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 258-271

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34889

Sensitivity and Uncertainty Analyses Applied to One-Dimensional Radionuclide Transport in a Layered Fractured Rock. Part I: Analytical Solutions and Local Sensitivities

A. Berge Gureghian, Yih-Tsuen Wu, Budhi Sagar, Richard B. Codell

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 272-296

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34890

Sensitivity and Uncertainty Analyses Applied to One-Dimensional Radionuclide Transport in a Layered Fractured Rock. Part II: Probabilistic Methods Based on the Limit-State Approach

Yih-Tsuen Wu, A. Berge Gureghian, Budhi Sagar, Richard B. Codell

Nuclear Technology / Volume 104 / Number 2 / November 1993 / Pages 297-308

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34891

Differences in Oxidation Behavior of Used CANDU Fuel During Prolonged Storage in Moisture-Saturated Air and Dry Air at 150°C

Kenneth M. Wasywich, William H. Hocking, David W. Shoesmith, Peter Taylor

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 309-329

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34893

Hydrogen Generation During Treatment of Simulated High-Level Radioactive Waste with Formic Acid

James A. Ritter, John R. Zamecnik, Chia-Lin W. Hsu

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 330-342

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34894

Corrosion of High-Level Waste Packaging Materials in Disposal Relevant Brines

Emmanuel Smailos

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 343-350

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34895

Desorption Kinetics of Radionuclides Fixed in Cement Matrix

T. M. Krishnamoorthy, S. N. Joshi, G. R. Doshi, R. N. Nair

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 351-357

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34896

Thermal Loading Studies Using Cooling Enhancement and Ventilation

George Danko

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 358-371

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34897

A Comparison of Glass Reaction at High and Low Glass Surface/Solution Volume

William L. Ebert, John K. Bates

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 372-384

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34898

Implications of Episodic Nonequilibrium Fracture-Matrix Flow on Repository Performance

John J. Nitao, Thomas A. Buscheck, Dwayne A. Chesnut

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 385-402

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34899

Gamma Radiolysis of Water Solutions Relevant to the Nuclear Fuel Waste Management Program

S. Sunder, H. Christensen

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 403-417

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34900

Repository-Heat-Driven Hydrothermal Flow at Yucca Mountain, Part I: Modeling and Analysis

Thomas A. Buscheck, John J. Nitao

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 418-448

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34901

Repository-Heat-Driven Hydrothermal Flow at Yucca Mountain, Part II: Large-Scale In Situ Heater Tests

Thomas A. Buscheck, John J. Nitao, Dale G. Wilder

Nuclear Technology / Volume 104 / Number 3 / December 1993 / Pages 449-471

Technical Paper / Special Issue on Waste Management / Radioactive Waste Management / dx.doi.org/10.13182/NT93-A34902