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Volume 77

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Number 1

NUFREQ/SLIP: An Improved Digital Computer Model for Predicting Nuclear Thermally Induced Flow Instabilities

Samir M. Sami, C. H. Le

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 7-17

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33947

Fission Product Tellurium Release Behavior Under Severe Light Water Reactor Accident Conditions

Jack L. Collins, Morris F. Osborne, R. A. Lorenz

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 18-31

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33948

SAFER03 and TRAC-BD1 Analyses of a ROSA-III Large-Break Experiment on a Boiling Water Reactor

Seihiro Itoya, Masami Kato, Nobuaki Abe, Hideo Nagasaka

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 32-45

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33949

Removal of Suspended Alumina Particles from Heavy Water by Electroadsorption on Fibrous Carbon Electrodes

Haim Tobias, Efraim Taragan, Yoram Oren, Abraham Soffer

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 46-49

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A33950

Cracking and Relocation of Mixed-Oxide Fast-Reactor Fuel

Timothy S. Roth, A. Biancheria

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 50-59

Technical Paper / Material / dx.doi.org/10.13182/NT87-A33951

Exposure Buildup Factors of High-Energy Gamma Rays for Water, Concrete, Iron, and Lead

Hideo Hirayama

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 60-67

Technical Paper / Radioisotopes and Isotope Separation / dx.doi.org/10.13182/NT87-A33952

Coal Analysis with Gamma Rays from Capture of 252Cf Neutrons—Experimental Equipment Designs and Results

Dick Duffey, Peter F. Wiggins

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 68-81

Technical Paper / Radioisotopes and Isotope Separation / dx.doi.org/10.13182/NT87-A33953

A Test of Some Condensation Models in the Presence of a Noncondensable Gas Against the ECOTRA Experiment

Philippe J. Vernier, Philippe Solignac

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 82-91

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33954

A Miniature Spark Counter for Public Communication and Education

Cheng-Hsin Mao, Pao-Shan Weng

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 92-96

Technical Paper / Analyse / dx.doi.org/10.13182/NT87-A33955

A Monte Carlo Model for On-Line Neutron Capture Prompt Gamma-Ray Analysis of Coal in Transmission Geometry

Y. L. Yuan, R. P. Gardner, K. Verghese

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 97-109

Technical Paper / Analyse / dx.doi.org/10.13182/NT87-A33956

Fission Gas Bubbles in Uranium-Aluminide Fuels

Gerard L. Hofman

Nuclear Technology / Volume 77 / Number 1 / April 1987 / Pages 110-115

Technical Note / Nuclear Fuel / dx.doi.org/10.13182/NT87-A33957

Number 2

  • Table of Contents
  • Authors(George Yadigaroglu, Hector A. Munera, Roger D. Spence, Anthony L. Wright, Michael F. Albert, Jack S. Watson, Robert P. Wichner, Horst Roepenack, Fritz U. Schlemmer, Gerhard J. Schlosser, Hiromichi Fumoto, Erich Zimmer, Erich R. Merz, Atsuyuki Suzuki, Ryohei Kiyose, Alexander P. Murray, C. Phillip McGinnis, Emory D. Collins, Reginald Hall, J. Keith Johnson, Alan M. Krichinsky, Bradley D. Patton, Joel T. Shor, Raymond J. Vedder, Thomas E. Blue, T. Courtney Roberts, Rolf F. Barth, Joseph W. Talnagi, Fazlul Alam, Ross C. Anderson, Kerry L. Basehore)

Transport of Pollutants: Summary Review of Physical Dispersion Models

George Yadigaroglu, Hector A. Munera

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 125-149

Critical Review / Nuclear Safety / dx.doi.org/10.13182/NT87-A33979

The Importance of Fission Production/Aerosol Interactions in Reactor Accident Calculations

Roger D. Spence, Anthony L. Wright

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 150-160

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33980

The Absorption of Gaseous Iodine by Water Droplets

Michael F. Albert, Jack S. Watson, Robert P. Wichner

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 161-174

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33981

Development of Thermal Plutonium Recycling

Horst Roepenack, Fritz U. Schlemmer, Gerhard J. Schlosser

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 175-186

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT87-A33982

Droplet Diameters and Axial Mixing in Pulse Columns in the Comparison of the Aqueous to Organic Continuous Mode of Operation

Hiromichi Fumoto, Erich Zimmer, Erich R. Merz, Atsuyuki Suzuki, Ryohei Kiyose

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 187-193

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A33983

Modeling Nuclear Decontamination Processes

Alexander P. Murray

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 194-209

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A33984

Development and Operation of a Unique Conversion/Solidification Process for Highly Radioactive and Fissile Uranium

C. Phillip McGinnis, Emory D. Collins, Reginald Hall, J. Keith Johnson, Alan M. Krichinsky, Bradley D. Patton, Joel T. Shor, Raymond J. Vedder

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 210-219

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT77-210

Boron-10 Concentration Measurements Using the Solid-State Nuclear Track Detector CR-39 and Automatic Image Analysis

Thomas E. Blue, T. Courtney Roberts, Rolf F. Barth, Joseph W. Talnagi, Fazlul Alam

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 220-226

Technical Paper / Radioisotopes and Isotope Separation / dx.doi.org/10.13182/NT87-A33986

Monte Carlo Departure from Nucleate Boiling Ratio Limit Development Using Few-Channel Thermal-Hydraulics Code Models

Ross C. Anderson, Kerry L. Basehore

Nuclear Technology / Volume 77 / Number 2 / May 1987 / Pages 227-230

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33987

Number 3

  • Table of Contents
  • Authors(Samir M. Sami, M. Kraitem, Yoichiro Shimazu, Yuzo Nakano, Yoshihisa Tahara, Tadayoshi Okayama, Kazuo Azekura, Constantine P. Tzanos, Toshiso Kosako, Junpei Matsumoto, Akira Sekiguchi, Nobuo Ohtani, Soju Suzuki, Shinso Takeda, Osamu Sato, Robert J. Quaiattini, Michael P. McGauley, Deborah L. Burns, Paul R. Tichler, Jiin-Shiung Horng, Wen-Shou Chuang, Ying-Chu Hoh, Brent J. Lewis, Dugald B. Duncan, Colin R. Phillips, Edmondo Zamorani, Simcha Stroes-Gascoyne, Lawrence H. Johnson, Dennis M. Sellinger, Klaus Rehme, Manuel González-Cuesta, David Okrent, Gerhard Karsten)
  • Public Reactions to Nuclear Power—Are There Critical Masses?(Gerald A. Schlapper)

A New Approach for Predicting Steam Volume Fraction in Transient Flow Boiling

Samir M. Sami, M. Kraitem

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 237-246

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33963

Development of a Compact Digital Reactivity Meter and a Reactor Physics Data Processor

Yoichiro Shimazu, Yuzo Nakano, Yoshihisa Tahara, Tadayoshi Okayama

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 247-254

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33964

Reactivity Analysis Model Based on Finite Difference Method for Three-Dimensional Fast Breeder Reactor Core Deformation

Kazuo Azekura

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 255-262

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33965

Liquid-Metal Fast Breeder Reactor Core Transient Modeling for Faster Than Real-Time Analysis

Constantine P. Tzanos

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 263-278

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33966

Measurements and Evaluations of Neutron Dose and Spectra at the Reactor Top of the Liquid-Metal Fast Breeder Type Reactor, JOYO

Toshiso Kosako, Junpei Matsumoto, Akira Sekiguchi+, Nobuo Ohtani, Soju Suzuki, Shinso Takeda, Osamu Sato

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 279-294

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33967

Conversion of Deuterium Gas to Heavy Water by Catalytic Isotopic Exchange Using Wetproof Catalyst

Robert J. Quaiattini, Michael P. McGauley, Deborah L. Burns, Paul R. Tichler

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 295-298

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A33968

A Semiempirical Equation for Estimating Thorium Nitrate Extraction by DHPSO from Nitric Acid Solution

Jiin-Shiung Horng, Wen-Shou Chuang, Ying-Chu Hoh

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 299-302

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A33969

Release of Iodine from Defective Fuel Elements Following Reactor Shut-down

Brent J. Lewis, Dugald B. Duncan, Colin R. Phillips

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 303-312

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT87-A33970

Water Corrosion and Release Mechanism of Cement Matrix Incorporating Simulated Medium-Level Waste

Edmondo Zamorani

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 313-319

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33971

The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel

Simcha Stroes-Gascoyne, Lawrence H. Johnson, Dennis M. Sellinger

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 320-330

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33972

On the Development of Turbulent Flow in Wall Subchannels of a Rod Bundle

Klaus Rehme

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 331-342

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33973

A Historical Perspective on Seismic Risk Assessment and Bayesian Updating

Manuel González-Cuesta, David Okrent

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 343-348

Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT87-A33974

Energy Dissipation in Nuclear Ceramic Materials

Gerhard Karsten

Nuclear Technology / Volume 77 / Number 3 / June 1987 / Pages 349-353

Technical Note / Material / dx.doi.org/10.13182/NT87-A33975