American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 77 / Number 1

Volume 77

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