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Volume 90

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Number 1

Table of Contents
Authors(Carolyn D. Heising, William S. Grenzebach, Edward C. Beahm, Steven R. Daish, William E. Shockley, Joram Hopenfeld, Paul G. Voillequé, Abdo A. Husseiny, Zeinab A. Sabri, S Keith Adams, Rodrigo J. Rodriguez, Bau-Shei Pei, Ge-Ping Yu, Guei-Ching Lin, Yin-Pang Ma, Imtiaz K. Madni, Erik G. Cazzoli, Mohsen Khatib-Rahbar, Richard D. Peters, Urban P. Jenquin, Langdon K. Holton, Jr., Sadao Hattori, Tadasu Takuma, Koshichi Nemoto, Masafumi Terada, Tamotsu Sano, Alois Höld)

A Computerized Diagnostic System for Nuclear Plant Control Rooms Based on Statistical Quality Control

Carolyn D. Heising, William S. Grenzebach

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 7-15

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34381

Iodine Partitioning in Pressurized Water Reactor Steam Generator Accidents

Edward C. Beahm, Steven R. Daish, William E. Shockley, Joram Hopenfeld

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 16-22

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34382

Measurements of Radioiodine Species in Samples of Pressurized Water Reactor Coolant

Paul G. Voillequé

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 23-33

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34383

Automation of Nuclear Power Plants

Abdo A. Husseiny, Zeinab A. Sabri, S. Keith Adams, Rodrigo J. Rodriguez

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 34-48

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34384

Assessment of the Safety Function for the Anticipated Transient without Trip Mitigation System Actuation Circuitry at Maanshan Nuclear Power Station

Bau-Shei Pei, Ge-Ping Yu, Guei-Ching Lin, Yin-Pang Ma

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 49-62

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34385

Assessment of Uncertainties in Early Off-Site Consequences from Nuclear Reactor Accidents

Imtiaz K. Madni, Erik G. Cazzoli, Mohsen Khatib-Rahbar

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 63-77

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34386

Measuring and Predicting Gamma Radiation from Radioactive Glass-Filled Canisters

Richard D. Peters, Urban P. Jenquin, Langdon K. Holton, Jr.

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 78-86

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34387

Studies on the Applicability of a Flow Coupler to a Liquid-Metal Fast Breeder Reactor Plant

Sadao Hattori, Tadasu Takuma, Koshichi Nemoto, Masafumi Terada, Tamotsu Sano

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 87-97

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34388

UTSG-2—A Theoretical Model Describing the Transient Behavior of a Pressurized Water Reactor Natural-Circulation U-Tube Steam Generator

Alois Höld

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 98-118

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34389

Number 2

Table of Contents
Authors(Hasna J. Khan, H. P. Chou, J. R. Lu, M. B. Chang, Jerry E. Dick, Vijay I. Nath, Erl Kohn, Thomas K. Min, Soedi Prawirosoehardjo, James P. Adams, Martin B. Sattison, Akihiko Inoue, Hermann Würz, Werner Eyrich, Hans-Joachim Becker, Yongsoo Hwang, P. L. Chambré, T. H. Pigford, W. W.-L. Lee, Fu-Long Chen, Shih-Hai Li, Peter Hofmann, Mario Enrique Markiewicz, José Luis Spino, Michael P. Manahan, Sr., Christopher Charles, Samuel H. Levine, Marcus H. Voth)
Radiation Detection and Measurement, 2nd Edition(William H. Miller)

A Distribution Parameter Derived for Rectangular Channels and Simulated Subchannel Geometry

Hasna J. Khan

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 125-141

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34409

A Three-Dimensional Space-Time Model and Its Use in Pressurized Water Reactor Rod Ejection Analyses

H. P. Chou, J. R. Lu, M. B. Chang

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 142-154

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34410

Event Sequence of a Severe Accident in a Single-Unit Candu Reactor

Jerry E. Dick, Vijay I. Nath, Erl Kohn, Thomas K. Min, Soedi Prawirosoehardjo

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 155-167

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34411

Frequency and Consequences Associated with a Steam Generator Tube Rupture Event

James P. Adams, Martin B. Sattison

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 168-185

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34412

Nuclear Fuel Reprocessing of (U,Pu)0₂ Fuel

Akihiko Inoue

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 186-190

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34413

A Nondestructive Method for Light Water Reactor Fuel Assembly Identification

Hermann Würz, Werner Eyrich, Hans-Joachim Becker

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 191-204

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34414

Brine Migration in a Salt Repository

Yongsoo Hwang, P. L. Chambré, T. H. Pigford, W. W.-L. Lee

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 205-214

Technical Paper / Radioacitive Waste Management / dx.doi.org/10.13182/NT90-A34415

Derivation of an Equation for Radionuclide Transport in Porous Media

Fu-Long Chen, Shih-Hai Li

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 215-225

Technical Paper / Radioacitive Waste Management / dx.doi.org/10.13182/NT90-A34416

Reaction Behavior of B₄C Absorber Material with Stainless Steel and Zircaloy in Severe Light Water Reactor Accidents

Peter Hofmann, Mario Enrique Markiewicz, José Luis Spino

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 226-244

Technical Paper / Matetial / dx.doi.org/10.13182/NT90-A34417

A Generalized Methodology for Obtaining Quantitative Charpy Data from Test Specimens of Nonstandard Dimensions

Michael P. Manahan, Sr., Christopher Charles

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 245-259

Technical Paper / Material / dx.doi.org/10.13182/NT90-A34418

Education and Training at the Pennsylvania State University Breazeale Reactor Over the Past 20 Years

Samuel H. Levine, Marcus H. Voth

Nuclear Technology / Volume 90 / Number 2 / May 1990 / Pages 260-265

Technical Paper / Education / dx.doi.org/10.13182/NT90-A34419

Number 3

Table of Contents
Authors(Parvez Salim, Yassin A. Hassan, Cliff B. Davis, Francesc Reventós, José Sánchez-Baptista, Alberto Pérez Navas, Pablo Moreno, Heikki Kantee, Harri Tuomisto, Vesa Yrjölä, Juan M. Cajigas, Thomas K. Blanchat, Yassin A. Hassan, Francesco D’Auria, Giorgio Maria Galassi, Jae Jun Jeong, Deog Yeon Oh, Hee Cheon No, Soon Heung Chang, Sung Jae Cho, Hwang Yong Jun, Yong Kwan Lee, José M. Martínez-Val,José M. Aragonés, Emilio Mínguez, José M. Perlado, Guillermo Velarde, Bhagi Purna Chandra Rao, Mandayam Tondanur Shyamsunder, Dipak Kumar Bhattacharya, Baldev Raj, Jorma Jokiniemi, Kimmo Koistinen, Taisto Raunemaa, Thiagarajan Gnanasekaran, Kandhalu Hari Mahendran, Raghavachary Sridharan, Vedaraman Ganesan, Govindaswami Periaswami, Cherian K. Mathews, A. Cihat Baytaṣ)
Preface: First International RELAP5 User Seminar(Yassin A. Hassan)
Theoretical and Experimental Methods of Heavy-Ion Physics

Modeling and Loss-of-Coolant Accident Analysis of a Nuclear Power Plant Using RELAP5/MOD2

Parvez Salim, Yassin A. Hassan

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 275-285

Technical Paper / RELAP/MOD2 / Nuclear Safety / dx.doi.org/10.13182/NT90-A34393

Pump Cavitation in Savannah River Reactors During Loss-of-Coolant Accidents

Cliff B. Davis

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 286-293

Technical Paper / RELAP/MOD2 / Nuclear Safety / dx.doi.org/10.13182/NT90-A34394

Transient Analysis in the Ascó Nuclear Power Plant Using RELAP5/MOD2

Francesc Reventós, José Sánchez-Baptista, Alberto Pérez Navas, Pablo Moreno

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 294-307

Technical Paper / RELAP/MOD2 / Nuclear Safety / dx.doi.org/10.13182/NT90-A34395

Application of RELAP5/MOD2 to Loviisa Nuclear Power Plant Overcooling Transients

Heikki Kantee, Harri Tuomisto, Vesa Yrjölä

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 308-315

Technical Paper / RELAP/MOD2 / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34396

The RELAP5-FORCE MOD2 Code, A Hydrodynamic Forcing Function Calculation Version of RELAP5

Juan M. Cajigas

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 316-325

Technical Paper / RELAP/MOD2 / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34397

A Comparison Study of the Westinghouse Model E Steam Generator Using RELAP5/MOD2 and RETRAN-02 Computer Codes

Thomas K. Blanchat, Yassin A. Hassan

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 326-339

Technical Paper / RELAP/MOD2 / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34398

Assessment of the RELAP5/MOD2 Code on the Basis of Experiments Performed in the LOBI Facility

Francesco D'auria, Giorgio Maria Galassi

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 340-355

Technical Paper / RELAP/MOD2 / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34399

FISA-2/WS, A Compact Real-Time Simulator for Two-Loop Pressurized Water Reactor Plants

Jae Jun Jeong, Deog Yeon Oh, Hee Cheon No, Soon Heung Chang, Sung Jae Cho, Hwang Yong Jun, Yong Kwan Lee

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 356-370

Technical Paper / RELAP/MOD2 / Fission Reactor / dx.doi.org/10.13182/NT90-A34400

An analysis of the Physical Causes of the Chernobyl Accident

José M. MartíNez-Val, José M. AragonéS, Emilio míNguez, José M. Perlado, Guillermo Velarde

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 371-388

Technical Paper / RELAP/MOD2 / Nuclear Safety / dx.doi.org/10.13182/NT90-A34401

Optimization of Eddy-Current Probes for Detection of Garter Springs in Pressurized Heavy Water Reactors

Bhagi Purna Chandra Rao, Mandayam Tondanur Shyamsunder, Dipak Kumar Bhattacharya, Baldev Raj

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 389-393

Technical Paper / RELAP/MOD2 / Nuclear Safety / dx.doi.org/10.13182/NT90-A34402

Experimental Verification of Hygroscopic Aerosol Growth in Reactor Accident Conditions

Jorma Jokiniemi, Kimmo Koistinen, Taisto Raunemaa

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 394-407

Technical Paper / RELAP/MOD2 / Nuclear Safety / dx.doi.org/10.13182/NT90-A34403

An Electrochemical Hydrogen Meter for Measurement of Dissolved Hydrogen in Liquid Sodium

Thiagarajan Gnanasekaran, Kandhalu Hari Mahendran, Raghavachary Sridharan, Vedaraman Ganesan, Govindaswami Periaswami, Cherian K. Mathews

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 408-416

Technical Paper / RELAP/MOD2 / Material / dx.doi.org/10.13182/NT90-A34404

A Comparison of Prediction and Tapucu Experimental Data for Determination of the Axial Velocity in the Gap Region

A. Cihat Baytaṣ

Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 417-425

Technical Paper / RELAP/MOD2 / Heat Transfer and fluid Flow / dx.doi.org/10.13182/NT90-A34405