ANS / Publications / Journals / Nuclear Technology

The Characteristics of the RBMK Core

Anna A. Afanasieva, Evgeniy V. Burlakov, Alexander V. Krayushkin, Andre V. Kubarev

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 1-9

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34825

Vessel Fluence Assessment with the EFLUVE Code and a Low-Fluence Fuel Management Scheme

François-David Rosset, Henri Schaeffer

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 10-18

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34826

Transient Thermal Analysis of a Space Reactor Power System

Michael J. Gaeta, Frederick R. Best

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 19-33

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34827

Time Domain Model Sensitivity in Boiling Water Reactor Stability Analysis Using TRAC/BF1

Jeffrey A. Borkowski, Gordon E. Robinson, Anthony J. Baratta, Matthew Kattic

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 34-48

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34828

Best-Estimate Methodology for Analysis of Anticipated Transients Without Scram in Pressurized Water Reactors

Luis Rebollo

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 49-65

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34829

Fission Product Transport and Behavior During Two Postulated Loss-of-Flow Transients in the Advanced Test Reactor

James P. Adams, Michael L. Carboneau, Donald L. Hagrman

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 66-78

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34830

Reactor Dynamics and Stability Analysis of a Burst-Mode Gas Core Reactor, Brayton Cycle Space Power System

Edward T. Dugan, Kiratadas Kutikkad

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 79-92

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34831

Separation and Concentration of Hydrogen Isotopes by a Palladium Alloy Membrane

Yasuo Suzuki, Shoji Kimura

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 93-100

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34832

Corrosion Product Particles in Boiling Water Reactor Condensates

Hans-Peter Hermansson, Göran Persson, Anneli Reinvall

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 101-113

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A34833

Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation

Joon Gi Ahn, Nam Zin Cho, Jung Eui Kuh

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 114-121

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT93-A34834

A Realistic Anticipated Transient Without Scram Evaluation of the Zorita Nuclear Power Plant

Luis Rebollo

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 122-130

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34835

Analysis of a Turbine Trip Transient with the Chinshan Plant Analyzer

Shih-Jen Wang, Chun-Sheng Chien, Jung-Yuh Jang

Nuclear Technology / Volume 103 / Number 1 / July 1993 / Pages 131-137

Technical Note / Reactor Operation / dx.doi.org/10.13182/NT93-A34836

Static and Dynamic Neutronic Analysis of a Burst-Mode, Multiple-Cavity Gas Core Reactor, Rankine Cycle Space Power System

Edward T. Dugan, Samer D. Kahook

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 139-156

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34839

An Efficient Nodal Method for Transient Calculations in Light Water Reactors

Jae-Woong Song, Jong-Kyung Kim

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 157-167

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34840

The Case for Endurance Testing of Sodium-Heated Steam Generators

A. T. Onesto, H. R. Zweig, D. C. Gibbs, R. D. Carlson, E. Rodwell, C. R. Kakarala

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 168-186

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34841

Preliminary Neutronics Calculations for Conversion of the Tehran Research Reactor Core from Heu to Leu Fuel

Seyed Mohammad R. Nejat

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 187-198

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34842

Effect of System Pressure on Reactor Power Limits Criteria

Kuo-Fu Chen

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 199-205

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34843

Modeling Condensation Steam Quenching Effects in an MSIV Closure Transient Using RETRAN-02-MOD002 With and Without Nonequilibrium Pressurizer Model Option and TRAC-BF1

B.D. Boyer, J. W. Hartzell,† S. Lider, G. E. Robinson, A. J. Baratta, A. J. Roscioli

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 206-219

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34844

Fuel Performance and Fission Product Release Studies for Defected Fuel Elements

Brent J. Lewis, Roderick D. MacDonald, Nicholas V. Ivanoff, Fernando C. Iglesias

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 220-245

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34845

Radiological Safety Experience in the Fabrication of Alloy Plate Fuels Bearing ²³³U/Pu

A. M. Bhagwat, K. V. Kamath, K. N. Kutty, G. R. Naik, K. K. Narayan, P. R. Pillai, G. J. Prasad, C. Ganguly

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 246-256

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34846

Estimation of Hydrogen Peroxide Decomposition Rates in the Boiling Water Reactor Primary Coolant Circuit

Chien C. Lin

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 257-261

Technical Paper / Material / dx.doi.org/10.13182/NT93-A34847

Evaluation of an Exponential Model for Germanium Detector Efficiencies

Willard G. Winn

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 262-273

Technical Paper / Radiation Application / dx.doi.org/10.13182/NT93-A34848

Optimization of Monte Carlo Calculations for Photon Sources from Actinides

L. L. Carter

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 274-287

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT93-A34849

The Influence of Optimum Power Level Change on Boration and Dilution Operations

Aquilino Senra Martinez, Eugenio De Andrade Oliveira

Nuclear Technology / Volume 103 / Number 2 / August 1993 / Pages 288-293

Technical Note / Reactor Operation / dx.doi.org/10.13182/NT93-A34850

Concept and Design of a Supercritical-Pressure, Direct-Cycle Light Water Reactor

Yoshiaki Oka, Sei-Ichi Koshizuka

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 295-302

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34852

On Chaotic Dynamics in Nuclear Engineering Systems

Dan Gabriel Cacuci

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 303-309

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34853

Simulation of Loss of RHR During Midloop Operations and the Role of Steam Generators in Decay Heat Removal Using the RELAP5/MOD3 Code

Yassin A. Hassan, Laxminarayan L. Raja

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 310-319

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34854

Gadolinium Neutron Capture Therapy

George A. Miller, Jr., Nolan E. Hertel, Bernard W. Wehring, John L. Horton

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 320-331

Technical Paper / Radiation Biology and Medicine / dx.doi.org/10.13182/NT93-A34855

A Theoretical Critical Heat Flux Model for Low-Pressure, Low-Mass-Flux, and Low-Steam-Quality Conditions

Wei-Hsiao Ho, Kuan-Chywan Tu, Bau-Shei Pei, Chin-Jang Chang

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 332-345

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A34856

Subcriticality of Two Uranyl Nitrate Flat Cylindrical Tanks Spaced in Air by ²⁵²Cf-Source-Driven Noise Analysis

J. T. Mihalczo, E. D. Blakeman, V. K. Paré, T. E. Valentine, D. J. Auslander

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 346-379

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT93-3

A Geometric Buckling Expression for Regular Polygons: I. Measurements in Low-Enriched UO₂-H₂O Lattices

Yoshinori Miyoshi, Masafumi Itagaki, Masanori Akai, Hideyuki Hirose, Masao Hashimoto

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 380-391

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT93-A34858

A Geometric Buckling Expression for Regular Polygons: II. Analyses Based on the Multiple Reciprocity Boundary Element Method

Masafumi Itagaki, Yoshinori Miyoshi, Hideyuki Hirose

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 392-402

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT93-A34859

Optimizing Feedwater Control System Performance with the Chinshan Plant Analyzer

Shih-Jen Wang, Chun-Sheng Chien

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 403-409

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A34860

The Dynamics of a Turbine-Driven Reactor Feedwater Pump and Identification of Related Parameters in the Kuosheng Power Station

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

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 410-416

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A34861

A Hybrid S_n-Diffusion Theory Computational Scheme for Efficient Neutronic Calculations of Externally Moderated Gas Core Reactors

Edward T. Dugan, Mohammed K. Alfakhar

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 417-425

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT93-A34862

Potential Application of Zircaloy Chemical Embrittlement to Volume Reduction of Spent-Fuel Cladding

Masafumi Nakatsuka

Nuclear Technology / Volume 103 / Number 3 / September 1993 / Pages 426-433

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34863