ANS / Publications / Journals / Nuclear Technology

Criticality Safety Analysis of a Calciner Exit Chute

C. F. Haught, B. Basoglu, R. W. Brewer, D. F. Hollenbach, A. D. Wilkinson, H. L. Dodds, R. L. Oxenham

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 3-13

Technical Paper / Special on Nuclear Criticality Safety / Nuclear Criticality Safety / dx.doi.org/10.13182/NT94-A34906

Simulation of Hypothetical Criticality Accidents Involving Homogeneous Damp Low-Enriched UO₂ Powder Systems

B. Basoglu, R. W. Brewer, C. F. Haught, D. F. Hollenbach, A. D. Wilkinson, H. L. Dodds, P. F. Pasqua

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 14-30

Technical Paper / Special on Nuclear Criticality Safety / Nuclear Criticality Safety / dx.doi.org/10.13182/NT94-A34907

Modeling of Central Reactivity Worth Measurements in Lady Godiva

Tracy R. Wenz, Robert D. Busch

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 31-36

Technical Note / Special on Nuclear Criticality Safety / Nuclear Criticality Safety / dx.doi.org/10.13182/NT94-A34908

TRIGA Mark II Benchmark Experiment, Part I: Steady-State Operation

Irena Mele, Matjaž Ravnik, Andrej Trkov

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 37-51

Technical Paper / Special on Nuclear Criticality Safety / Fission Reactor / dx.doi.org/10.13182/NT94-A34909

TRIGA Mark II Benchmark Experiment, Part II: Pulse Operation

Irena Mele, Matjaž Ravnik, Andrej Trkov

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 52-58

Technical Paper / Special on Nuclear Criticality Safety / Fission Reactor / dx.doi.org/10.13182/NT94-1

The Quenching of Hydrogen/Air Flames in Obstructed and Multicompartment Configurations by Partial Inertization

Johan G. Visser, W. Paul M. Mercx, George L. C. M. Vayssier

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 59-69

Technical Paper / Special on Nuclear Criticality Safety / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34911

Transient Analysis and Startup Simulation of a Thermionic Space Nuclear Reactor System

Mohamed S. El-Genk, Huimin Xue, Dmitry Paramonov

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 70-86

Technical Paper / Special on Nuclear Criticality Safety / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34912

On the Use of Expert Judgments to Estimate the Pressure Increment in the Sequoyah Containment at Vessel Breach

Sumeet Chhibber, George E. Apostolakis, David Okrent

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 87-103

Technical Paper / Special on Nuclear Criticality Safety / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34913

Conceptual Design Loss-of-Coolant Accident Analysis for the Advanced Neutron Source Reactor

N. C. J. Chen, Mark W. Wendel, Graydon L. Yoder, Jr.

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 104-122

Technical Paper / Special on Nuclear Criticality Safety / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34914

An Experimental Study of Gravity-Driven Countercurrent Two-Phase Flow in Horizontal and Inclined Channels

K. H. Lillibridge, S. M. Ghiaasiaan, S. I. Abdel-Khalik

Nuclear Technology / Volume 105 / Number 1 / January 1994 / Pages 123-134

Technical Paper / Special on Nuclear Criticality Safety / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34915

Interaction of Iodine with Preoxidized Stainless Steel

J. Abrefah, H. F. G. De Abreu, F. Tehranian, Y. S. Kim, D. R. Olander

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 137-144

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34918

Incipient Fault Detection and Identification in Process Systems Using Accelerated Neural Network Learning

Alexander G. Parlos, Jayakumar Muthusami, Amir F. Atiya

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 145-161

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34919

TRACG Transient Analysis Code—Three-Dimensional Kinetics Model Implementation and Applicability for Space-Dependent Analysis

Yutaka Takeuchi, Yukio Takigawa, Hitoshi Uematsu, Shigeo Ebata, James C. Shaug, Bharat S. Shiralkar

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 162-183

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34920

The Optimization of Squared-Off Cascades for Isotope Separation

Chuntong Ying, Edward Von Halle

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 184-189

Technical Paper / Enrichment and Reprocessing / dx.doi.org/10.13182/NT94-A34921

Scaling Laws and Design Aspects of a Natural-Circulation-Cooled Simulated Boiling Water Reactor Fuel Assembly

Rudi Van De Graaf, T. H. J. J. Van Der Hagen, Robert F. Mudde

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 190-200

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34922

Sandor Benedek

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 201-215

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34923

An Assessment of the Critical Heat Flux Approaches of Thermal-Hydraulic System Analysis Codes Using Bundle Data from the Heat Transfer Research Facility

Min Lee, Lih-Yih Liao

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 216-230

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34924

A Modeling Study of the PMK-NVH Integral Test Facility

Borut Mavko, Iztok Parzer, Stojan Petelin

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 231-252

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34925

On a Simplified Two-Phase Slug Flow Model

Yu-Wen Wang, Bau-Shei Pei, Wei-Keng Lin

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 253-260

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34926

The Effect of Dissolved Gas Bubble Nucleation on Natural Convection Heat Transfer in Narrow Channels

Wei-Wu Chao, Jay F. Kunze, Weimin Dai, Sudarshan K. Loyalka

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 261-270

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34927

Empirical Model Development and Validation with Dynamic Learning in the Recurrent Multilayer Perceptron

Alexander G. Parlos, Kil T. Chong, Amir F. Atiya

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 271-290

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34928

Evaluation of the Reactivity Expansion Defect for Small Solid-Core Reactors and Components

Salim Jahshan, Samim Anghaie

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 291-292

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT94-A34929

Thermal Performance Test of a Coaxial Double-Tube Hot-Gas Duct

Ikuo Ioka, Yoshiyuki Inagaki, Kazuhiko Kunitomi, Yoshiaki Miyamoto, Kunihiko Suzuki

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 293-299

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34930

Secondary-Side Feed-and-Bleed Effectiveness in Pressurized Water Reactors

Alessandro Annunziato

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 301-321

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34932

Use of Post-Chernobyl Data from Norway to Validate the Long-Term Exposure Pathway Models in the Accident Consequence Code MACCS

Ulf Tveten

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 322-333

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34933

The Composition of Aerosols Generated During a Severe Reactor Accident: Experimental Results from the Power Burst Facility Severe Fuel Damage Test 1-4

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

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 334-345

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34934

Fabrication of (Pu_0.55U_{0 .45})C Fuel Pellets for the Second Core of the Fast Breeder Test Reactor in India

Chaitanyamoy Ganguly, Parameshwar Venkappa Hegde, Gyan Chand Jain

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 346-354

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34935

Prototype Oxide Breeder Tests in the Fast Flux Test Facility

Allen L. Pitner, Brent C. Gneiting, Ronald B. Baker, Samuel L. Hecht

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 355-365

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34936

Fission Product Release from Uranium-Aluminum Alloy Fuel in SLOWPOKE-2 Reactors

Brent J. Lewis, Anne C. Harnden-Gillis, Leslie G. I. Bennett

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 366-380

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34937

Modeling of Transient Thermal-Hydraulic Phenomena in a Once-Through Steam Generator During Auxiliary Feedwater Injection

B. K. Kamboj, S. M. Ghiaasiaan, S. I. AbdeL-Khalik

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 381-394

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34938

An Analytical Model of the Swirl Vane Steam Separator for Boiling Water Reactors

Curt M. Betts, Mark R. Galvin, Janet R. Green,† V. Melvin Guymon, Stephen M. Slater,‡, Andrew C. Klein

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 395-410

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34939

Thermal-Hydraulic Analysis of the Advanced Neutron Source Reactor Refueling Process

Yousri Elkassabgi, Graydon L. Yoder, Wallace R. Gambill

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 411-420

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34940

Effective Thermal Conductivity and Edge Conductance Model for a Spent-Fuel Assembly

Randall D. Manteufel, Neil E. Todreas

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 421-440

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34941

Elements of a Radioactive Waste Management Course

Audeen W. Fentiman

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 441-446

Technical Paper / Education / dx.doi.org/10.13182/NT94-A34942

Self-Initialization Algorithm of the Kuosheng Plant Analyzer

Shih-Jen Wang, Chun-Sheng Chien, Suh-Chyn Jeng

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 447-456

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT94-A34943

Congo Red/Polyvinyl Alcohol Film Dosimeter for Gamma Rays and Electrons

Woon Hyuk Chung

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 457-458

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT94-A34944