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Volume 69

Number 1

Nuclear Power Plant Site Selection: A Case Study

Yaakoy Lugasi, Abraham Mehrez, Zilla Sinuany-Stern

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 7-13

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33590

Improvements in Compartment Fire Modeling and Simulation of Experiments

Gary Chung, Nathan Siu, George Apostolakis

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 14-26

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33591

Sensitivity and Uncertainty Analyses for the Accident Sequence Precursor Study

Mohammad Modarres, Theodore W. Cadman, Erasmia Lois, Alan R. Gardner

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 27-35

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33592

Radioactive Source Term Models in a Compartment Fire Code

Marcel Y. Ballinger, Peter C. Owczarski

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 36-43

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT85-A33593

Status of Qualification of High-Temperature Reactor Fuel Element Spheres

Werner Heit, Hans Huschka, Wilhelm Rind, Günter G. Kaiser

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 44-54

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33594

Behavior of Breached Light Water Reactor Spent Fuel Rods in Air and Inert Atmospheres at 229°C

Robert E. Einziger, James A. Cook

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 55-71

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33595

Measurement of Cladding Temperatures with Loss-of-Fluid-Test Thermocouples in the COSIMA Blowdown Test Facility

Gottfried Class, Klaus Hain, Rainer Meyder

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 72-81

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33596

An Experimental Study of Rod Bundle Dispersed-Flow Film Boiling with High-Pressure Water

David G. Morris, Charles B. Mullins, Graydon L. Yoder, Jr.

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 82-93

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33597

An Empirical Mixing Model for Pressurized Thermal Shock Applications

V. K. (Bindi) Chexal, Jason Chao, Robert E. Nickell, Timothy J. Griesbach

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 94-99

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33598

Assessment of TRAC Codes with Dartmouth College Countercurrent Flow Tests

U. S. Rohatgi

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 100-106

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33599

Development of a New Measurement Method for Fast Breeder Reactor Fuel Burnup Using a Shielded lon Microprobe Analyzer

Mineo Mizuno, Yuji Enokido, Ichiro Unno, Keiichi Kono, Sadamu Yamanouchi, Toshiyuki Itaki

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 107-113

Technical Paper / Technique / dx.doi.org/10.13182/NT85-A33600

Initial Results for the Experimental Evaluation of a Nuclear Waste Repository Source Term Model

B. P. McGrail, L. A. Chick, G. L. McVay

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 114-118

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33601