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

Home / Publications / Journals / Nuclear Technology / Volume 191 / Number 1

Volume 191

Number 1

Variation of Burnable Neutron Absorbers in a Heavy Water–Moderated Fuel Lattice: A Potential to Improve CANDU Reactor Operating Margins

Paul K. Chan, Stephane Paquette, Hugues W. Bonin

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 1-14

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-67

Study on Heat Removal Capacity of PCCS of Advanced Passive PWR During Severe Accidents

Lili Tong, Jie Zou, Jun Tao, Xuewu Cao

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 15-26

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-93

DART Analysis of Irradiation Behavior of U-Mo/Al Dispersion Fuels

Bei Ye, Jeff Rest, Yeon Soo Kim, Gerard Hofman, Benoit Dionne

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 27-40

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-56

Intelligent Analysis of Low-Count Scintillation Spectra Using Support Vector Regression and Fuzzy Logic

Miltiadis Alamaniotis, Sangkyu Lee, Tatjana Jevremovic

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 41-57

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-75

Corrosion Behavior of Zirconium, Titanium, and Their Alloys in Simulated Dissolver Solution of Fast Breeder Reactor Spent Nuclear Fuel Using Zircaloy-4 Mock-Up Dissolver Vessel

J. Jayaraj, K. Thyagarajan, C. Mallika, U. Kamachi Mudali

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 58-70

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT14-90

Particle Production by Rotational Abrasion Between Graphite Spheres

Raymond S. Troy, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 71-91

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT14-109

Design and Laboratory Evaluation of Future Elongation and Diameter Measurements at the Advanced Test Reactor

K. L. Davis, D. L. Knudson, J. L. Rempe, J. C. Crepeau, S. Solstad

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 92-105

Technical Note / Materials for Nuclear Systems / dx.doi.org/10.13182/NT14-60

Degradation of Nylon 6,6 Fire-Suppression Casing from Plutonium Glove Boxes Under Alpha and Neutron Irradiation

D. W. Millsap, M. E. Cournoyer, S. Landsberger, J. Tesmer, Y. Wang

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 106-112

Technical Note / Materials for Nuclear Systems / dx.doi.org/10.13182/NT14-47

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use