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Volume 90

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