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Volume 74

Number 1

Automatic Determination of Pressurized Water Reactor Core Loading Patterns That Maximize Beginning-of-Cycle Reactivity Within Power-Peaking and Burnup Constraints

Gregory H. Hobson, Paul J. Turinsky

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 5-13

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33814

Shielding Designs for Pressurized Water Reactors in France

Gilles Champion, Josette Forestier, Thérèse Vergnaud

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 14-26

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33815

A Study on Fuel Rod Vibration Induced by Baffle Jet Flow

Kazuichiro Seki, Shigeru Kuwabara, Katsumi Tanimura, Shinsuke Matsumoto, Masao Toba

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 27-37

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33816

Stability Tests at Browns Ferry Unit 1 Under Single-Loop Operating Conditions

Jose March-Leuba, Richard T. Wood, Pedro J. Otaduy, Clayton O. McNew

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 38-52

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33817

Experience in the Use of Probabilistic Safety Analysis for the Development of Safety Concepts for Commercial High-Temperature Reactors

Wolfgang Kröger, Johannes P. Wolters

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 53-64

Technical Paper / Neuclear Safety / dx.doi.org/10.13182/NT86-A33818

Computer Simulation of a Large-Scale Reprocessing Plant for Safeguards

G. Spannagel, M. J. Canty, E. A. Kern

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 65-75

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT86-A33819

Role of Surface Vaporization in Low-Volatility Fission Product Release Experiments

A. B. Reynolds, J. L. Kelly, S. T. Kim

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 76-83

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT86-A33820

The Effect of Fast-Neutron Irradiation on the Fatigue-Crack Growth Behavior of Several Austenitic Stainless Steels and Weldments

Lee A. James

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 84-92

Technical Paper / Material / dx.doi.org/10.13182/NT86-A33821

Simulation of Heat and Mass Transfer in Molten Core/Concrete Interactions

I. K. Paik, S. I. Abdel-Khalik

Nuclear Technology / Volume 74 / Number 1 / July 1986 / Pages 93-103

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT86-A33822