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Volume 65

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Number 1

Dryout of an Inductively Heated Bed of Steel Particles with Subcooled Flow from Beneath the Bed

F. P. Tsai, J. Jakobsson, I. Catton, V. K. Dhir

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 10-15

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33367

Modes of Heat Removal from a Heat-Generating Debris Bed

D. Squarer, L. E. Hochreiter, A. T. Pieczynski

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 16-22

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33368

On the Pattern of Water Penetration into a Hot Particle Bed

D. H. Cho, Donn R. Armstrong II, S. H. CHAN

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 23-31

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33369

Radiative Contribution to the Heat Transfer in Liquid Urania

M. Bober, J. Singer, K. Wagner

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 32-35

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33370

On the Location and Mechanisms of Dryout in Top-Fed and Bottom-Fed Particulate Beds

G. Hofmann

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 36-45

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33371

Mechanical Behavior of SNR-300 Reactor Vessel Components Under Postaccident Heat Removal Conditions

Hartwig Laue, Klaus Hermann Kerz

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 46-52

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33372

A Coolability Model for Postaccident Nuclear Reactor Debris

Ronald J. Lipinski

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 53-66

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33373

Cooling of Debris Beds

Leopold Barleon, Klaus Thomauske, Heinrich Werle

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 67-86

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33374

Light Water Reactor Debris from Severe In-Pile Transient Tests

Richard R. Hobbins, Beverly A. Cook, Richard E. Mason

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 87-91

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33375

Steam Generator Leak Detection in Liquid-Metal Fast Breeder Reactors by Chemical Methods

George J. Licina, Dwight R. Springer, Prodyot Roy

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 92-101

Technical Paper / Postaccident Debris Cooling / Nuclear Safety / dx.doi.org/10.13182/NT84-A33376

Nonsoluble Fission Product Residues, Crud, and Fine Chips of Zircaloy Cladding in Headend Process of Nuclear Fuel Reprocessing

Kozo Gonda, Koichiro Oka, Keiichi Hayashi

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 102-108

Technical Paper / Postaccident Debris Cooling / Fuel Cycle / dx.doi.org/10.13182/NT84-A33377

Chemical Interactions Between UO2 and Zircaloy-4 from 1000 to 2000°C

Wolfgang Dienst, Peter Hofmann, Deborah K. Kerwin-Peck

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 109-124

Technical Paper / Postaccident Debris Cooling / Nuclear Fuel / dx.doi.org/10.13182/NT84-A33378

On the Applicability of Analytical Solutions of the Transport Equation for the Migration of Substances in Groundwater-Bearing Horizons

Marion Petschel, Dietmar Zappe

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 125-130

Technical Paper / Postaccident Debris Cooling / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33379

The Effect of Composition of Selected Groundwaters from the Basin and Range Province on Plutonium, Neptunium, and Americium Speciation

Terry F. Rees, Jess M. Cleveland, Kenneth L. Nash

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 131-137

Technical Paper / Postaccident Debris Cooling / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33380

Investigation of Oxides Formed in the Corrosion of SUS-304 in High-Temperature Water Through the Measurement of Evolved Hydrogen and Radiochemical Analyses

Enzo Tachikawa, Michio Hoshi, Chiaki Sagawa, Chushiro Yonezawa, Mikio Nakashima

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 138-145

Technical Paper / Postaccident Debris Cooling / Material / dx.doi.org/10.13182/NT84-A33381

Scaling Criteria for Two-Phase Flow Loops and Their Application to Conceptual 2×4 Simulation Loop Design

Gunol Kocamustafaogullari, Mamoru Ishii

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 146-160

Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33382

Paint Decontamination Kinetics

Edward W. Thornton

Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 161-167

Technical Paper / Postaccident Debris Cooling / Technique / dx.doi.org/10.13182/NT84-A33383

Number 2

Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors

Leon C. Walters, B. R. Seidel, J. Howard Kittel

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 179-231

Critical Review / dx.doi.org/10.13182/NT84-A33408

Risk-Oriented Analysis of the German Prototype Fast Breeder Reactor SNR-300: Off-Site Accident Consequence Model and Results of the Study

Anton Bayer, Joachim Ehrhardt

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 232-249

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33409

An Investigation of BWR/4 Parallel Channel Effects During a Hypothetical Loss-of-Coolant Accident for Both Intact and Broken Jet Pumps

Mohammad R. Fakory, R. T. Lahey, Jr.

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 250-265

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33410

Vapor Transport of Fission Products in Postulated Severe Light Water Reactor Accidents

Daniel Cubicciotti, Bal Raj Sehgal

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 266-291

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33411

Optimization and Analysis of Low-Leakage Core Management for Pressurized Water Reactors

Yi-Chiang Chang, Alexander Sesonske

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 292-304

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT84-A33412

Recovery of Noble Metals from Fission Products

George A. Jensen, A. M. Platt, George B. Mellinger, William J. Bjorklund

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 305-324

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT84-A33413

Application of Dynamic Simulation to Radwaste Evaporator Systems

Habib Amin, K. C. Chiu, David W. James

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 325-331

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33414

Using Titanium Oxide for Cobalt Removal from High-Temperature Water

Fumio Kawamura, Kiyomi Funabashi, Makoto Kikuchi, Katsumi Ohsumi

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 332-339

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33415

A Multiple Regression Equation for Calculated keff Bias Errors by Criticality Code System

Yasushi Nomura, Takanori Shimooke

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 340-349

Technical Paper / Criticality Safety / dx.doi.org/10.13182/NT84-A33416

Technique for Producing a Continuous Interference-Free Stream of Argon-41 in Air

Tung-Tse Tseng, William A. Jester

Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 350-353

Technical Note / Analyse / dx.doi.org/10.13182/NT84-A33417

Number 3

  • Table of Contents
  • Authors(Tohru Mitsutake, Shigeaki Tsunoyama, Shigeru Kanemoto, Hideaki Namba, Shirley A. Sandoz, Shigeaki Tsunoyama, Tohru Mitsutake, Shigeo Ebata, Shirley A. Sandoz, Wan-Li Zhong, J. Weisman, Susumu Ninomiya, Fumio Ohtsuka, Hiromichi Nei, Osamu Takikawa, Mituo Harata, Robert A. Fjeld, Thomas J. Overcamp, Ken Amano, Kotaro Inoue, C. D. Andriesse, R. H. J. Tanke, Robert P. Schuman, Berthold-Günter Brodda, Erich Richard Merz, Takashi Honda, Akira Minato, Katsumi Ohsumi, Hideo Matsubayashi, Shi-chune Yao, M. J. Loftus, L. E. Hochreiter, Yassin A. Hassan, James G. Rice, Jong H. Kim, Charles Hantouche)
  • Neutron Radiography, Proceedings of the First World Conference, San Diego, California, December 7–10, 1981(Raymond L. Murray)
  • Irradiation Technology(K. Linga Murty)

Core Stability Test Analysis Using the Autoregressive Model

Tohru Mitsutake, Shigeaki Tsunoyama, Shigeru Kanemoto, Hideaki Namba, Shirley A. Sandoz

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 365-373

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33391

Reactor Core Stability Analysis for a Boiling Water Reactor by a Transient Model

Shigeaki Tsunoyama, Tohru Mitsutake, Shigeo Ebata, Shirley A. Sandoz

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 374-382

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33392

Automated Control Rod Programming in Boiling Water Reactor Cores

Wan-Li Zhong, J. Weisman

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 383-394

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33393

Development of a Sodium Vapor Pressure Meter Using Beta-Alumina Ceramics

Susumu Ninomiya, Fumio Ohtsuka, Hiromichi Nei, Osamu Takikawa, Mituo Harata

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 395-401

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33394

Electrically Enhanced Deposition of a Confined Aerosol in the Presence of Ionizing Radiation

Robert A. FJeld, Thomas J. Overcamp

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 402-408

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33395

Analysis of Coolant Pressure Fluctuation and Induced Vibration of Liquid-Metal Fast Breeder Reactor Fuel Pins

Ken Amano, Kotaro Inoue

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 409-414

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33396

Dominant Factors in the Release of Fission Products from Overheated Urania

C. D. Andriesse, R. H. J. Tanke

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 415-421

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33397

Leach Testing of Idaho National Engineering Laboratory Waste Forms in a Gamma Field

Robert P. Schuman

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 422-431

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33398

The Leaching Behavior of Zircaloy Cladding and Its Impact on the Conditioning of Waste for Final Disposal

Berthold-Günter Brodda, Erich Richard Merz

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 432-437

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33399

Radioactive Contamination of Carbon Steel in a Boiling Water Reactor

Takashi Honda, Akira Minato, Katsumi Ohsumi, Hideo Matsubayashi

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 438-443

Technical Paper / Material / dx.doi.org/10.13182/NT84-A33400

Hydraulics of Blocked Rod Bundles

Shi-Chune Yao, M. J. Loftus, L. E. Hochreiter

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 444-453

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33401

An Improved Multidimensional Finite Difference Scheme for Predicting Stratified Horizontal Pipe Flow

Yassin A. Hassan, James G. Rice, Jong H. Kim

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 454-461

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33402

Comparative Study of Measurements by Means of Gamma Thermometer Strings with Fission Chamber Measurements

Charles Hantouche

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 462-466

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT84-A33403