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

Home / Publications / Journals / Nuclear Technology / Volume 129 / Number 3

Volume 129

Number 3

Neutron Fluence, Dosimetry and Damage Response Determination in In-Core/Ex-Core Components of the VENUS CEN/SCK LWR Using 3-D Monte Carlo Simulations: NEA's VENUS-3 Benchmark

J. Manuel Perlado, Jaime Marian, Jesús García Sanz

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 285-296

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3063

The Chemistry of Iodine in Containment

Jungsook Clara Wren, Joanne M. Ball, Glenn A. Glowa

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 297-325

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT129-297

Depletion Analysis of Mixed-Oxide Fuel Pins in Light Water Reactors and the Advanced Test Reactor

Gray S. Chang, John M. Ryskamp

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 326-337

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3065

Numerical Simulation of Accumulated Steam Generator Tube Sheet Damage and Loose Part Impact Distributions

Liang Shi, J. Michael Doster, Charles W. Mayo

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 338-355

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3066

Testing a Passive Autocatalytic Recombiner in the Surtsey Facility

Thomas K. Blanchat, Asimios C. Malliakos

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 356-373

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3067

Development of the INSPECT Model for the Prediction of Iodine Volatility from Irradiated Solutions

Shirley Dickinson, Howard E. Sims

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 374-386

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT00-A3068

Measurements of the Radiolytic Oxidation of Aqueous CsI Using a Sparging Apparatus

C. B. Ashmore, D. Brown, S. Dickinson, H. E. Sims

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 387-397

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT00-A3069

Estimating the Impurity Concentration Factor on the Boiling Heat Transfer Surface of a Simulated Steam-Generator Tube-Support-Plate Crevice Using an In Situ High-Temperature Conductivity Measurement Technique

Hirotaka Kawamura, Hideo Hirano

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 398-406

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT00-A3070

A Novel Method for Energy Production Using 242mAm as a Nuclear Fuel

Yigal Ronen, Menashe Aboudy, Dror Regev

Nuclear Technology / Volume 129 / Number 3 / March 2000 / Pages 407-417

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT00-A3071

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use