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Volume 174

Number 1 | Number 2 | Number 3

Number 1

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

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

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

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

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

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

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

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

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

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

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

Number 2

Foreword: Special Issue on the SCALE Nuclear Analysis Code System

John C. Wagner

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

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

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

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

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

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

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

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

Number 3

Foreword: Special Issue on the 2009 TOUGH2 Symposium

George J. Moridis

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

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

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

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

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

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

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

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

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

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

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

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

 
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