ANS / Publications / Journals / Nuclear Technology

Parametric Study of Sloshing Effects in the Primary System of an Isolated Lead-Cooled Fast Reactor

Marti Jeltsov, Walter Villanueva, Pavel Kudinov

Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 1-10

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-8

Reactivity Swing as a Function of Burnup for Uranium-Fueled Fast Reactors

Staffan Qvist

Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 11-27

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-30

Neutron Multiplicity Measurements With ³He Alternative: Straw Neutron Detectors

Sanjoy Mukhopadhyay, Ronald Wolff, John Meade, Ryan Detweiler, Richard Maurer, Stephen Mitchell, Paul Guss, Jeffrey L. Lacy, Liang Sun, Athanasios Athanasiades

Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 28-35

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-12

Irradiation of Minor Actinide–Bearing Uranium-Plutonium-Zirconium Alloys up to ~2.5 at. %, ~7 at. %, and ~10 at. % Burnups

Hirokazu Ohta, Takanari Ogata, Dimitrios Papaioannou, Vincenzo V. Rondinell, Marc Masson, Jean-Luc Paul

Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 36-51

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-50

Investigation of Effect of Ballooned Fuel Pins on Quenching Behavior: Design of Experiment and Preliminary Analysis

O. S. Gokhale, B. P. Puranik, A. K. Ghosh

Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 52-64

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-31

Identification of Nonconservative Subregions in Empirical Models Demonstrated Using Critical Heat Flux Models

Joshua Kaizer

Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 65-71

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-38

Uncertainty Quantification of Concrete Utilized in Dry Cask Storage

Ryan Kelly, Pavel Tsvetkov, Sunil Chirayath, John Poston, Evans Kitcher

Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 72-87

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-155

New Approach for Fatigue Damage Monitoring Based on Actual Operating History of Nuclear Power Plants

Hee-Jin Shim, Chang-Kyun Oh, Hyun-Su Kim, Myung-Hwan Boo, Jong-Jooh Kwon

Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 88-96

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT13-150