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Volume 106

Number 1 | Number 2 | Number 3

Number 1

Monte Carlo Simulation of the Massachusetts Institute of Technology Research Reactor

Everett L. Redmond II, Jacquelyn C. Yanch, Otto K. Harling

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 1-14

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A34946

Assessment of the Impact of Neutronic/Thermal-Hydraulic Coupling on the Design and Performance of Nuclear Reactors for Space Propulsion

Shashikant M. Aithal, Tunc Aldemir, Kambiz Vafai

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 15-30

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A34947

Conceptual Design Station Blackout and Loss-of-Flow Accident Analyses for the Advanced Neutron Source Reactor

C. D. Fletcher, L. S. Ghan, J. C. Determan, H. H. Nielsen

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 31-45

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34948

Simultaneous Bottom and Top-Down Rewetting Calculations with the CATHARE Code

Jan Bartak, Timo Haapalehto

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 46-59

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34949

Mixed-Oxide Fuel Fabrication Technology and Experience at the Belgonucléaire and CFCa Plants and Further Developments for the MELOX Plant

Didier Haas, Alain Vandergheynst, Jean van Vliet, Robert Lorenzelli, Jean-Louis Nigon

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 60-82

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34950

A Two-Dimensional Finite Element Method Large Eddy Simulation for Application to Turbulent Steam Generator Flow

Freddie J. Davis, Jr., Yassin A. Hassan

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 83-99

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34951

Visualization of the Lower Plenum Anomaly in the Westinghouse AP600 Reactor

Thomas D. Radcliff, William S. Johnson, J. Roger Parsons, Douglas E. Ekeroth

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 100-109

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34952

Development of In-Service Inspection Priorities for Pressurized Water Reactor High-Pressure Injection System Components

Truong V. Vo, Doyle R. Edwards

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 110-124

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT94-A34953

Development of the Kuosheng Plant Analyzer and Its Assessment with Plant Data

Shih-Jen Wang, Chun-Sheng Chien, Chia-Yu Wang, Tsu-Chi Lyie, Shih-Hsiin Chang, Der-Chyuan Wang, Suh-Chyn Jeng

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 125-134

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT94-A34954

The Scaling Parameter of the Sigmoid Function in Artificial Neural Networks

Tim H. J. J. van der Hagen

Nuclear Technology / Volume 106 / Number 1 / April 1994 / Pages 135-138

Technical Note / Reactor Control / dx.doi.org/10.13182/NT94-A34955

Number 2

Evaluation of a Severe Accident Management Strategy for Boiling Water Reactors—Drywell Flooding

Donghan Yu, Leiming Xing, William E. Kastenberg, David Okrent

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 139-154

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34971

Mean Importance Measures for Groups of Events in Fault Trees

F. Eric Haskin, Min Huang, M. Kent Sasser, Desmond W. Stack

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 155-167

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34972

Analysis of the Chemical Behavior of Iodine in the Suppression Tank of the LOFT Facility During Experiment LP-FP-2 with IODE and IMPAIR-2/M

Luis E. Herranz, Jesús Polo

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 168-176

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34973

Interaction of Nickel Ions with Magnetite Particles in High-Temperature Water

Kostadin A. Dinov, Kenkichi Ishigure, Daisuke Hiroishi, Chihiro Matsuura

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 177-185

Technical Paper / Material / dx.doi.org/10.13182/NT94-A34974

Modeling of Bubbly and Annular Two-Phase Flow in Subchannel Geometries with BACCHUS-3D/TP

Maurizio Bottoni, Robert W. Lyczkowski

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 186-201

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34975

Theoretical Modeling of Forced Convection Condensation of Steam in a Vertical Tube in the Presence of a Noncondensable Gas

Mansoor Siddique, Michael W. Golay, Mujid S. Kazimi

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 202-215

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34976

Optimal Reliable Control System Design for Steam Generators in Pressurized Water Reactors

Wencheng Wu, Chaung Lin

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 216-224

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34977

Accelerating Learning of Neural Networks with Conjugate Gradients for Nuclear Power Plant Applications

Jaques Reifman, Javier E. Vitela

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 225-241

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34978

Fuzzy Power Control Algorithm for a Pressurized Water Reactor

Yung-Joon Hah, Byong-Whi Lee

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 242-253

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34979

Low-Power Experimental Study of the Demand Surface for Annular Geometry Fuel Elements with Upflow of Coolant

Allen C. Smith, James E. Blake, Michael T. Childerson, Ted R. Ohrn, Robert M. Privette

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 254-260

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34980

Film Dosimeters Based on Methylene Blue and Methyl Orange in Polyvinyl Alcohol

Woon Hyuk Chung, Arne Miller

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 261-264

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT94-A34981

Number 3

A Study of Plateout Fission Product Behavior During a Large-Scale Pipe Rupture Accident in a High-Temperature Gas-Cooled Reactor

Kazuhiro Sawa, Isao Murata, Shusaku Shiozawa, Mikio Matsumoto

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 265-273

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34957

Modeling of Heat Transfer to Nuclear Steam Supply System Heat Sinks and Application to Severe Accident Sequences

Kune Y. Suh

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 274-291

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34958

Xenon Stability Analysis Using the Generalized Nyquist Criterion

You-Cho Choi, Goon-Cherl Park, Chang-Hyun Chung

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 292-299

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34959

A Study on Boiling Water Reactor Regional Stability from the Viewpoint of Higher Harmonics

Yutaka Takeuchi, Yukio Takigawa, Hitoshi Uematsu

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 300-314

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34960

Use of an Influence Diagram and Fuzzy Probability for Evaluating Accident Management in a Boiling Water Reactor

Donghan Yu, William E. Kastenberg, David Okrent

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 315-325

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34961

Trace Metal Assay of Uranium Silicide Fuel

M. J. Kulkarni, A. A. Argekar, S. K. Thulasidas, B. A. Dhawale, B. Rajeswari, V. C. Adya, P. J. Purohit, G. Neelam, T. R. Bangia, A. G. Page, M. D. Sastry, R. H. Iyer

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 326-333

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34962

Numerical Analysis for Microstructure Change of a Light Water Reactor Fuel Pellet at High Burnup

Takanori Kameyama, Tetsuo Matsumura, Motoyasu Kinoshita

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 334-341

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34963

Internal Flaws in the Silicon Carbide Coating of Fuel Particles for High-Temperature Gas-Cooled Reactors

Kazuo Minato, Hironobu Kikuchi, Kousaku Fukuda, Nobuyuki Suzuki, Hiroshi Tomimoto, Nobu Kitamura, Mitsunobu Kaneko

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 342-349

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34964

An Evaluation of the Deployment of AIROX-Recycled Fuel in Pressurized Water Reactors

Salim N. Jahshan, Thomas J. McGeehan

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 350-359

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34965

Transport Phenomena and Occupational Consequences of a Tritium Release

Dong H. Nguyen

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 360-372

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT94-A34966

Measurement of Neutron Radiation Exposure of Commercial Airline Pilots Using Bubble Detectors

Brent J. Lewis, Richard Kosierb, Tom Cousins, Donald F. Hudson, Georges Guéry

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 373-383

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT94-A34967

Development of Software for the Microsimulator for the KO-RI Nuclear Power Plant Unit 2

Ho Seok, Hee Cheon No, Sung Jae Cho, Sang Doug Park, Hwang Young Jun, Yong Kwan Lee

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 384-396

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT94-A34968

Verification of Feedwater System Models of the Kuosheng Plant Analyzer

Shih-Jen Wang, Chun-Sheng Chien, Shih-Hsiin Chang, Suh-Chyn Jeng

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 397-406

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34969

 

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