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Volume 103

Number 3

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 Sn-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