American Nuclear Society
Join ANS|Member Center|ANS Store|Contact Us
Home

Home / Publications / Journals / Nuclear Technology / Volume 103 / Number 2

Volume 103

Number 2

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

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use