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Volume 190

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Number 1

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

Number 2

Probability and Consequences of Nuclear Criticality at a Geologic Repository—I: Conceptual Overview for Screening

Rob P. Rechard

Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 97-126

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-40

Probability and Consequences of Nuclear Criticality at a Geologic Repository—II: Potential Repository in Volcanic Tuff as an Example

Rob P. Rechard

Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 127-160

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-41

A Numerical Solution of the Reeks-Hall Equation for Particulate Concentration in Recirculating Turbulent Fluid Flow

Giang N. Nguyen, Sudarshan K. Loyalka

Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 161-173

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-81

Potential Impacts of Modeling Full Reactor Cores Using Combined Fuel Performance and Thermal Hydraulics Codes

Ian Porter, Travis W. Knight, Patrick Raynaud

Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 174-182

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-100

Gamma-Ray Simulated Spectrum Deconvolution of a LaBr3 1- ×1-in. Scintillator for Nondestructive ATR Fuel Burnup On-Site Predictions

Jorge Navarro, Terry A. Ring, David W. Nigg

Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 183-192

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-4

Novel Approach to Extracting Transuranic Elements in Molten Salt Electrorefining

Yoshiharu Sakamura, Masatoshi Iizuka, Tadafumi Koyama, Shinichi Kitawaki, Akira Nakayoshi

Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 193-206

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT14-64

Release of Radioactive Materials from Simulated High-Level Liquid Waste at Boiling Accident in Reprocessing Plant

S. Tashiro, G. Uchiyama, Y. Amano, H. Abe, Y. Yamane, K. Yoshida

Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 207-213

Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT14-57

Number 3

Experiments on the Effects of a Spacer Grid in Air-Water Two-Phase Flow

Joshua Wheeler, Ted Worosz, Seungjin Kim

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 215-224

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-69

Considerations in the Practical Application of the Multisensor Conductivity Probe for Two-Phase Flow

Matt Bernard, Ted Worosz, Seungjin Kim, Chris Hoxie

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 225-235

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-70

Thermal Evaluation of Alternate Shipping Cask for Irradiated Experiments

Donna Post Guillen

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 236-244

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-62

Thermal Predictions of the AGR-2 Experiment with Variable Gas Gaps

Grant L. Hawkes, James W. Sterbentz, Binh Pham

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 245-253

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-73

Natural Circulation in Heat Removal System During Loss-of-Flow Accident Based on Initial Conceptual Design

Si Y. Lee, L. Larry Hamm, Frank G. Smith III

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 254-263

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-86

Experiments in Cap-Bubbly Two-Phase Flows for Two-Group IATE Development

Ted Worosz, Seungjin Kim, Chris Hoxie

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 264-273

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-71

Estimation of Shear-Induced Lift Force in Laminar and Turbulent Flows

Aaron M. Thomas, Jun Fang, Jinyong Feng, Igor A. Bolotnov

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 274-291

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-72

Modification of SCWR Assembly Designs with Coupled MCNP5/SCA Methods to Promote Safer Operation

Christopher R. Hughes, Oswaldo Pelaez, Duwayne Schubring, Kelly A. Jordan

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 292-300

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-74

Experimental Investigation of Inverted Annular Film Boiling in a Rod Bundle During Reflood Transient

L. Mohanta, M. P. Riley, F. B. Cheung, S. M. Bajorek, J. M. Kelly, K. Tien, C. L. Hoxie

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 301-312

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-77

An Advanced One-Dimensional Finite Element Model for Incompressible Thermally Expandable Flow

Rui Hu

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 313-322

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-78

The Modeling of Advanced BWR Fuel Designs with the NRC Fuel Depletion Codes PARCS/PATHS

A. Wysocki, A. Ward, A. Manera, T. Downar, Y. Xu, J. March-Leuba, C. Thurston, N. Hudson, A. Ireland

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 323-335

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-79

Experimental Studies of Spacer Grid Thermal Hydraulics in the Dispersed Flow Film Boiling Regime

M. P. Riley, L. Mohanta, F. B. Cheung, S. M. Bajorek, K. Tien, C. L. Hoxie

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 336-344

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-80

Effects of SiC and Graphene Oxide Nanoparticle–Coated Surfaces on Quenching Performance

Kyung Mo Kim, Seung Won Lee, In Cheol Bang

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 345-358

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-82

On the Steady Mechanical Response of a Heterogeneous Fuel Plate

W. R. Marcum, T. V. Holschuh, T. K. Howard

Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 359-375

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-61

 
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