Home / Publications / Journals / Nuclear Technology / Volume 74

Volume 74

Number 1

Table of Contents
Authors(Gregory H. Hobson, Paul J. Turinsky, Gilles Champion, Josette Forestier, Thérèse Vergnaud, Kazuichiro Seki, Shigeru Kuwabara, Katsumi Tanimura, Shinsuke Matsumoto, Masao Toba, Jose March-Leuba, Richard T. Wood, Pedro J. Otaduy, Clayton O. McNew, Wolfgang Kröger, Johannes P. Wolters, G. Spannagel, M. J. Canty, E. A. Kern, A. B. Reynolds, J. L. Kelly, S. T. Kim, Lee A. James, I. K. Paik, S. I. Abdel-Khalik)
Neutron Transmutation Doping of Semiconductor Materials(Kaj Heydorn)
Principles of Radiation Shielding(G. Hehn)

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

Number 2

Table of Contents
Authors(Hack Yeong Chung, Soon Heung Chang, Satoshi Suzuki, Kohyu Fukunishi, Shoichi Kishi, Yuichiro Yoshimoto, Kunikazu Kishimoto, Steven J. Eckert, Kenneth A. Loparo, Zvi S. Roth, Alois Bleier, Karl Heinz Neeb, Eike Gelfort, Joachim Mischke, Kohtaro Ueki, Yoshihito Namito, Takayoshi Fuse, Yassin A. Hassan, Subhash Chandra, P. C. Cacciabue, A. Amendola, G. Cojazzi, T. Rothfuchs, D. R. Olander, Yossi Bushlin, Dov Ingman, Amos Notea, Hector A. Munera, George Yadigaroglu)
Comments On “Analysis Of ⁶⁰Co Gamma-Ray Transport Through Air By Discrete-Ordinates Codes"(Peter Jacob)
Pulsed Neutron Scattering(Donald R. Harris)
MOS (Metal Oxide Semiconductor) Physics and Technology(A. R. Wazzan)

Development of a Combined Algorithm of On-Line Instrument Failure Detection with an Improved Generalized Likelihood Ratio Method and Suboptimal Control on a PWR Pressurizer

Hack Yeong Chung, Soon Heung Chang

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 113-131

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33797

Applicability of a Multivariable Autoregressive Method to Boiling Water Reactor Core Stability Estimation

Satoshi Suzuki, Kohyu Fukunishi, Shoichi Kishi, Yuichiro Yoshimoto, Kunikazu Kishimoto

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 132-138

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33798

An Application of Nonlinear Filtering to Instrument Failure Detection in a Pressurized Water Reactor

Steven J. Eckert, Kenneth A. Loparo, Zvi S. Roth

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 139-151

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33799

Evaluation of the Tritium Content in Light Water Reactor Control and Absorber Rods to Obtain Data for the Fuel Cycle Backend

Alois Bleier, Karl Heinz Neeb, Eike Gelfort, Joachim Mischke

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 152-163

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33800

Measurement of Dose Rates and Monte Carlo Analysis of Neutrons in a Spent-Fuel Shipping Vessel

Kohtaro Ueki, Yoshihito Namito, Takayoshi Fuse

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 164-175

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33801

Analysis of FLECHT and FLECHT-SEASET Reflood Tests with RELAP5/MOD2

Yassin A. Hassan*

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 176-188

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33802

The Influence of Particle Phase Size on the Disassembly Accident Transient in Fast Reactors

Subhash Chandra

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 189-194

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33803

Dynamic Logical Analytical Methodology Versus Fault Tree: The Case Study of the Auxiliary Feedwater System of a Nuclear Power Plant

P. C. Cacciabue, A. Amendola, G. Cojazzi

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 195-208

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33804

In Situ Investigations on the Impact of Heat Production and Gamma Radiation with Regard to High-Level Radioactive Waste Disposal in Rock Salt Formations

T. Rothfuchs

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 209-214

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33805

Oxidation of UO₂ by High-Pressure Steam

D. R. Olander

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 215-217

Technical Paper / Material / dx.doi.org/10.13182/NT86-A33806

Moments Analysis Method for the Determination of Dimensions from Radiographs

Yossi Bushlin, Dov Ingman, Amos Notea

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 218-228

Technical Paper / Technique / dx.doi.org/10.13182/NT86-A33807

On Farmer’s Line, Probability Density Functions, and Overall Risk

Hector A. Munera, George Yadigaroglu

Nuclear Technology / Volume 74 / Number 2 / August 1986 / Pages 229-232

Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT86-A33808

Number 3

Table of Contents
Authors(Dov Ingman, Leib Reznik, Seung Min Baek, Hee Cheon No, In Yong Park, Tunc Aldemir, Don W. Miller, I. A. Papazoglou, N. Z. Cho, R. A. Bari, Gerd Porsch, Joachim Fleisch, Bernd Heits, Takashi Murakami, Tsunetaka Banba, Haruto Nakamura, Giovanni Bidoglio, Alfonso De Plano, John F. Relyea, David P. Trott, C. V. McIntyre, Craig G. Rieger, Alexander P. Murray, R. E. Williford)
Analysis of Graphite-Hydrogen-Methane Kinetics Above 1660 K

An Approach of Statistical Thermodynamics to Effects of Coherent Blockages of Reactor Core Coolant Channels

Dov Ingman, Leib Reznik

Nuclear Technology / Volume 74 / Number 3 / September 1986 / Pages 243-259

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33827

A Nonequilibrium Three-Region Model for Transient Analysis of Pressurized Water Reactor Pressurizer

Seung Min Baek, Hee Cheon No, In Yong Park

Nuclear Technology / Volume 74 / Number 3 / September 1986 / Pages 260-266

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33828

The Availability of Neutron Channels and Power Range Monitoring Systems with In Situ Detection of Channel Degradation

Tunc Aldemir, Don W. Miller

Nuclear Technology / Volume 74 / Number 3 / September 1986 / Pages 267-271

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33829