ANS / Publications / Journals / Nuclear Technology

Enhanced Simmer Neutronics Tool for Studying Fast Reactor Distorted Core Configurations

Sandra Poumerouly, Gérald Rimpault

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 1-17

Technical Paper / Accident Analysis and Consequences / dx.doi.org/10.13182/NT11-A11675

Numerical Modeling of Flow in the Condensate Polisher Vessel of a Nuclear Reactor, with Applications to PVNGS

Ashish Sharma, Jeffrey Brown, Harindra J. S. Fernando

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 18-28

Technical Paper / One-Phase Fluid Flow / dx.doi.org/10.13182/NT11-A11676

Safety Analysis for Hot Gas Duct Vessel in HTR-PM

Xiaotian Li, Xiaowei Li, Li Shi, Zhengming Zhang, Shuyan He

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 29-40

Technical Paper / One-Phase Fluid Flow / dx.doi.org/10.13182/NT11-A11677

Improved Simulations of Heat Transfer in Liquid-Metal Flows

Constantine P. Tzanos

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 41-50

Technical Paper / Heat Transfer / dx.doi.org/10.13182/NT11-A11678

Qualification of the RELAP5/PARCS Code for BWR Stability Events Prediction

Tomasz Kozlowski, Joanna Peltonen

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 51-63

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A11679

Observation of the Dynamics of Nuclear Systems Using Sliding Mode Observers

Günyaz Ablay, Tunc Aldemir

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 64-76

Technical Paper / Instrumentation and Control Systems / dx.doi.org/10.13182/NT11-A11680

Enhancement of Decontamination Performance of Impurities for Uranyl Nitrate Hexahydrate Crystalline Particles by Crystal Purification Operation

Masaumi Nakahara, Tsutomu Koizumi, Kazunori Nomura

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 77-84

Technical Paper / Chemical Reprocessing / dx.doi.org/10.13182/NT11-A11681

Diffusion Model for Electrolytic Reduction of Uranium Oxides in a Molten LiCl-Li₂O Salt

Supathorn Phongikaroon, Steven D. Herrmann, Michael F. Simpson

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 85-93

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT174-85

Impacts of Elevated Temperatures on Bentonite Extrusion and Cesium Transport in the Excavated Damaged Zone

R. A. Borrelli, Olivier Thivent, Joonhong Ahn

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 94-108

Technical Paper / Geochemistry and Ground Transport of RW / dx.doi.org/10.13182/NT11-A11683

Behavior of Actinide Elements and Fission Products in Recovery of Uranyl Nitrate Hexahydrate Crystal by Cooling Crystallization Method

Masaumi Nakahara, Tsutomu Koizumi, Kazunori Nomura

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 109-118

Technical Paper / Radiochemistry / dx.doi.org/10.13182/NT11-A11684

Development and Testing of a Nanotech Nuclear Battery for Powering MEMS Devices

Eric V. Steinfelds, James S. Tulenko

Nuclear Technology / Volume 174 / Number 1 / April 2011 / Pages 119-123

Technical Paper / Energy Conversion Systems Using Radioisotopes / dx.doi.org/10.13182/NT11-A11685

Foreword: Special Issue on the SCALE Nuclear Analysis Code System

John C. Wagner

Nuclear Technology / Volume 174 / Number 2 / May 2011 / Page 125

dx.doi.org/10.13182/NT11-A11716

SCALE 6: Comprehensive Nuclear Safety Analysis Code System

S. M. Bowman

Nuclear Technology / Volume 174 / Number 2 / May 2011 / Pages 126-148

Technical Paper / Special Issue on the SCALE Nuclear Analysis Code System / Reactor Safety / dx.doi.org/10.13182/NT10-163

Resonance Self-Shielding Methodologies in SCALE 6

Mark L. Williams

Nuclear Technology / Volume 174 / Number 2 / May 2011 / Pages 149-168

Technical Paper / Special Issue on the SCALE Nuclear Analysis Code System / Reactor Physics / dx.doi.org/10.13182/NT09-104

Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE

Ian C. Gauld, Georgeta Radulescu, Germina Ilas, Brian D. Murphy, Mark L. Williams, Dorothea Wiarda

Nuclear Technology / Volume 174 / Number 2 / May 2011 / Pages 169-195

Technical Paper / Special Issue on the SCALE Nuclear Analysis Code System / Fuel Cycle and Management / dx.doi.org/10.13182/NT11-3

Reactor Physics Methods and Analysis Capabilities in SCALE

Mark D. DeHart, Stephen M. Bowman

Nuclear Technology / Volume 174 / Number 2 / May 2011 / Pages 196-213

Technical Paper / Special Issue on the SCALE Nuclear Analysis Code System / Reactor Physics / dx.doi.org/10.13182/NT174-196

Monte Carlo Criticality Methods and Analysis Capabilities in SCALE

Sedat Goluoglu, Lester M. Petrie, Jr., Michael E. Dunn, Daniel F. Hollenbach, Bradley T. Rearden

Nuclear Technology / Volume 174 / Number 2 / May 2011 / Pages 214-235

Technical Paper / Special Issue on the SCALE Nuclear Analysis Code System / Reactor Safety / dx.doi.org/10.13182/NT10-124

Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE

B. T. Rearden, M. L. Williams, M. A. Jessee, D. E. Mueller, D. A. Wiarda

Nuclear Technology / Volume 174 / Number 2 / May 2011 / Pages 236-288

Technical Paper / Special Issue on the SCALE Nuclear Analysis Code System / Radiation Protection / dx.doi.org/10.13182/NT174-236

Monte Carlo Shielding Analysis Capabilities with MAVRIC

Douglas E. Peplow

Nuclear Technology / Volume 174 / Number 2 / May 2011 / Pages 289-313

Technical Paper / Special Issue on the SCALE Nuclear Analysis Code System / Radiation Protection / dx.doi.org/10.13182/NT174-289

Foreword: Special Issue on the 2009 TOUGH2 Symposium

George J. Moridis

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 315-316

dx.doi.org/10.13182/NT11-A11741

Estimation of Humidity During Tunnel Ventilation - Supported by TOUGH2 Calculations of Liquid, Vapor, and Heat Transport

Joachim Poppei, Gerhard Mayer, Nicolas Hubschwerlen, Guillaume Pépin, Jacques Wendling

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 317-326

Technical Note / TOUGH2 Symposium / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A11742

Natural Convection in Tunnels at Yucca Mountain and Impact on Drift Seepage

N. Halecky, J. Birkholzer, P. Peterson

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 327-341

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11743

Chemical Evolution of Bentonite Buffer in a Final Repository of Spent Nuclear Fuel During the Thermal Phase

Aku Itälä, Markus Olin

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 342-352

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11744

Simulation of Gas Transfer at the Scale of a Disposal Cell in the Context of High-Level and Long-Lived Radwaste Disposal in a Deep Clay Formation During the Operating Phase

E. Treille, J. Wendling, F. Plas

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 353-363

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11745

Computation of the Couplex-Gaz Exercise with TOUGH2-MP: Hydrogen Flow and Transport in the Pore Water of a Low-Permeability Clay Rock Hosting a Nuclear Waste Repository

Keni Zhang, Jean Croisé, Gerhard Mayer

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 364-374

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11746

A Turbulent Transport Network Model in MULTIFLUX Coupled with TOUGH2

G. Danko, D. Bahrami, J. Birkholzer

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 375-400

Technical Paper / TOUGH2 Symposium / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A11747

Thermohydraulic Analysis of Gas Generation in a Disposal Facility for Vitrified High-Level Radioactive Waste in Boom Clay

Janez Perko, Eef Weetjens

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 401-410

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11748

Comparison of Numerical Tools Through Thermo-Hydro-Gas Transport Modeling for a Geological Repository in Boom Clay

L. Yu, E. Weetjens, J. Perko, D. Mallants

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 411-423

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11749

Numerical Simulation of Atmospheric Carbonation of Concrete Components in a Deep Geological Radwaste Disposal Site During Operating Period

L. Trotignon, P. Thouvenot, I. Munier, B. Cochepin, E. Piault, E. Treille, X. Bourbon, S. Mimid

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 424-437

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11750

Bentonite Alteration Due to Thermal-Hydro-Chemical Processes During the Early Thermal Period in a Nuclear Waste Repository

Tianfu Xu, Rainer Senger, Stefan Finsterle

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 438-451

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11751

Injection of Nuclear Rocket Exhaust and Water into a Deep Unsaturated Zone

Clay A. Cooper, David L. Decker

Nuclear Technology / Volume 174 / Number 3 / June 2011 / Pages 452-459

Technical Paper / TOUGH2 Symposium / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A11752