Annual Meeting 2015 / Volume 112

ANS Officer

Meeting Officials, National Program Committee

Full Issue

Opening Plenary: Nuclear Technology: An Essential Part of the Solution

ANS President’s Special Session

Accelerator Applications: General

Dynamic System Simulation of Fissile Solution Systems

Christy M. Day, Steven K. Klein (LANL)

Colloid Rates of Radionuclides in Cooling Water of the 120-GeV Proton Accelerator Facilities at Fermilab, U.S.A.

Hiroshi Matsumura (KEK), Shun Sekimoto (Kyoto Univ), JASMIN Collaborators (KEK, Kyoto Univ, JAEA, Fermilab, Shimizu Corp.)

Waste Management for Decommissioning–Panel

Decommissioning and Environmental Sciences: General

Remediation of an Atomic Testing Era Laboratory

Dustin G. Miller (JG Management Systems)

Phenix Nuclear Power Plant Dismantling Start

F. Dominjon, J. P. Grandjean, F. Laurent (CEA)

Concurrent Assessment of Exposure to Workers in Virtual Decommissioning Environments

KwanSeong Jeong, ByungSeon Choi, JeiKwon Moon, Dongjun Hyun, Jonghwan Lee, IkJune Kim, GeunHo Kim (KAERI)

Focus on Communications: Endorsing Nuclear Energy–Panel

Focus on Communications: Improving our Advocacy–Panel

Education and Training: General

A Course on Condensed Matter Nuclear Science

George Miley (Univ of Illinois, Urbana-Champaign)

3D Virtual Research Reactor in Oculus Rift with LEAP Interactivity

Yoshinori Satoh (Univ of Illinois, Urbana-Champaign, Toshiba Co.), Rizwan-uddin (Univ of Illinois, Urbana-Champaign)

Distance Education of Reactor Laboratory at Missouri S&T

M. Yousaf, T. Akyurek, A. Alajo, S. Usman (Missouri Univ of Science and Technology)

International Status of Used Fuel and HLW Management: A Review of the 2015 International High-Level Radioactive Waste Management Conference–Panel

Environmental Monitoring of Nuclear Sites: Aspect Importance and Challenges–Panel

University Research in Fuel Cycles and Waste Management

Krypton Removal from the Off-Gas Stream Using the Hollow Carbon Based Nanosorbent

Sachin U. Nandanwar, Kai Coldsnow, Vivek Utgikar, D. Eric Aston (Univ of Idaho), Piyush Sabharwall (INL)

Protection of Zirconium Fuel Cladding by Aluminum Surface Modification

James Carr, Gokul Vasudevamurthy (VCU)

Computational Study of Self-Association of Tri-n-butyl Phosphate in n-Dodecane

Quynh N. Yo, Mikael Nilsson, Hung D. Nguyen (Univ of California, Irvine)

Adsorption of I₂ from Off-Gases from Used-Fuel Reprocessing Plants

Yue Nan (Syracuse Univ), Austin P. Ladshaw, Sotira Yiacoumi (Georgia Tech), Costas Tsouris (Georgia Tech, ORNL), David W. DePaoli (ORNL), Lawrence L. Tavlarides (Syracuse Univ)

Effects of Graphical Information on Public Perception toward Nuclear Energy

Ishoc U. Salaam, John M. Swanson, Sama Bilbao y León (VCU)

Direct Calculation of Concentration-dependent Activity Coefficient of UCl₃ in Molten LiCl-KCl

Wentao Zhou, Jinsuo Zhang (Ohio State Univ)

f-Element Complexation in Mixed Extractant UNF Reprocessing

Brian J. Gullekson, Vanessa E. Holfeltz, Alena Paulenova (Oregon State Univ), Artem V. Gelis (ANL)

Chlorination of Actinide and Rare Oxides for Application to Continuous pyroChemical Reprocessing

Abraham Jurovitzki, Michael Simpson (Univ of Utah)

Fuel Cycle Simulators

Binary Formulation of Decay Equations

Anthony M. Scopatz, Paul P. H. Wilson (Univ of Wisconsin, Madison), Cameron R. Bates (Univ of California, Berkeley)

Dynamic Resource Exchange Performance in Cyclus

Matthew J. Gidden, Paul P. H. Wilson (Univ of Wisconsin, Madison)

Using Spatial Flux Calculations to Improve the Fluence-Based Neutron Balance Approach

Cem Bagdatlioglu, Erich Schneider, Robert Flanagan (Univ of Texas, Austin)

Cymetric – A Fuel Cycle Metrics Tool for Cyclus

Anthony Scopatz, Arrielle Opotowsky, Paul P. H. Wilson (Univ of Wisconsin, Madison)

Cyclus Graphical User Interface User Experience Testing

Robert Flanagan, Erich Schneider (Univ of Texas, Austin)

Are There Customers in the U.S. for Advanced Nuclear Reactors?–Panel

Recycle and Reuse of Used Nuclear Fuel Resources

Feasibility Study for Select Isotope Recovery from La Hague

Sven Bader (AREVA)

In-situ Quantitative Analysis for Mixed Nd-Pr-Sm Lanthanides in LiCl-KCl Molten Eutectic Using Spectroscopic Techniques

Young Taek Jee (KAIST), Bong Young Kim (KAERI), Jong-Il Yun (KAIST)

Development of a Separation Process for Spent Fuel Containing Polymers

Olivier Fiquet, Aziza Chairat, Alexandre Ghionzoli (CEA)

Removal of Cs Ions from Aqueous Solution by Titanate Nanomaterials

Jing Fu, Dejun Liu, Peng Zhan, Tian Luo (State Nuclear Power Research Institute)

Cyclus Users–Tutorial

Hybrid Energy: Combining Nuclear and Other Energy Sources

Zero-Greenhouse-Gas Hydrocarbon Liquid Fuels Production

Charles Forsberg (MIT)

Overview of U.S. DOE Research and Development of Nuclear-Renewable Hybrid Energy Systems

Shannon M. Bragg-Sitton, Richard Boardman (INL)

Improving Nuclear System Economics using Firebrick Resistance-Heated Energy Storage (FIRES)

Daniel C. Stack, Charles Forsberg (MIT)

Nuclear-Renewable Hybrid Energy System for Reverse Osmosis Desalination Process\

Jong Suk Kim, Humberto E. Garcia (INL)

Thermoeconomic Analysis for Nuclear-Renewable Hybrid Energy System with Hydrogen Production

Lauren Boldon (RPI), Piyush Sabharwall, Cristian Rabiti, Shannon M. Bragg-Sitton (INL), Li Liu (RPI)

Nuclear Renewable Oil Shale System Development Pathway

Daniel Curtis, Charles Forsberg (MIT)

Cyclus Archetype Developers–Tutorial

Fuel Cycle and Waste Management: General–I

Moving from Closed to Open Fuel Cycle within the UK while Keeping Future Fuel Cycle Options Open

Fiona Rayment, Tim Tinsley, Robin Taylor, Robert Gregg (NNL)

Developments in Fuel Fabrication R&D within the UK

Daniel Mathers, Richard Stainsby, Emma Johnston, David Goddard (NNL)

Remote Area Modular Monitoring (RAMM) for Nuclear and Radiological Facilities

Hanchung Tsai, Brian Craig, Yung Y. Liu, James Shuler (ANL)

Parametric Analysis and Optimization using Multivariate Regression Analysis and Genetic Algorithms

Akansha Kumar, Pavel Tsvetkov (TAMU)

Evaluation of Eu Sorption onto TiO₂ Impurities in Natural Systems

Dejun Liu, Peng Zhan, Jing Fu, Tian Luo (State Nuclear Power Research Institute)

MAXUS® Corrosion Performance in Spent Fuel Pool Environments

Matthew L. Eyre (Eyre Nuclear Energy Consultancy), K. Scot Leuenroth (Curtiss Wright Corp.), Xavier Clausse (Nikkei Niigata Company), Toshiaki Yamazaki, Aaron Herfurth (Nikkeikin Aluminum Core Technology Co.)

Fuel Cycle and Waste Management: General—II

Storage of TMI-2 and Other Damaged Fuels at the Idaho Nuclear Technology and Engineering Center

Mark Argyle, Allan Carlson, Allan Christensen, Randy Fadeley, Greg Hall, James Stalnaker (CH2M-Washington Group Idaho)

An Optimization Methodology in Nuclear Reactor Design using Genetic Algorithms and Regression Analysis

Akansha Kumar, Pavel Tsvetkov (TAMU)

A Clash of Cultures – An Independent’s Lessons from the Current WIPP Mess

Norbert T. Rempe (ng(o)3)

Implementation of PFLOTRAN into the Waste Isolation Pilot Plant Performance Assessment

HeeHo Park, Glenn Hammond (SNL)

Early Stages of Cement Hydration in Brine Containing MgO: Preliminary Data on pH Changes and Implications for Actinide Chemistry

J. F. Lucchini, M. K. Richman, J. J. Swanson, D. T. Reed (LANL)

Fusion Energy: General

Plasma Current Stability Code (PCSC) Based on the Coupling Analysis of EMF-Eddy Current-Plasma Control

Shahab Ud-Din Khan, Yuntao Song (Chinese Academy of Sciences), Salah Ud-Din Khan (King Saud Univ)

Review of the Industrial Isotope Production in First Colliding-Beam Fusion Breeder Reactor Operating Well Above “Critical Energy”

Bogdan C. Maglich, Dan W. Scott, Tim Hester, James Nering (CALSEC)

Extreme Learning Machine Method Based Optimization of Ta Content in CLAM Steel

Longfeng Shen, Liqin Hu (Univ of Science and Technology of China, Chinese Academy of Sciences), Xiangwei Zhai (Chinese Academy of Sciences)

A Hydrogen Sensor for Liquid-Metal Breeding Blankets

Iuri Nicolotti (DENERG), Marco Utili (ENEA UTIS), Lugi Candido, Massimo Zucchetti (DENERG)

Human Factors, Instrumentation, and Controls: General—I

A Study on a Framework to Evaluate Operating Support Systems in NPPs

Moon Kyoung Choi, Poong Hyun Seong (KAIST)

Method for Detecting Stuck Fuel Element in a Pebble-bed Reactor

Hongbing Liu, Dong Du (Tsinghua Univ, Key Laboratory for Advanced Materials Processing Technology), Peng Shen (Henan Energy and Chemical Industry Group Co.)

Detection of Fuel-Elements for the Fuel-Handling System in a High Temperature Gas-Cooled Pebble Bed Reactor

Ayada He, Hongbing Liu, Dong Du (Tsinghua Univ, Key Laboratory for Advanced Materials Processing Technology)

An Application of Functional Modeling to the Prediction for Abnormal Conditions of Safety Critical Component in Standby State in Nuclear Power Plants

Young Gyu No, Seung Geun Kim, Poong Hyun Seong (KAIST)

Model-based Software Development Process with CASE Tool for NPP Safety Systems

Chang Ho Kim, Joo Hyun Cho, Se Do Sohn, Seung Min Baek (KEPCO E&C)

Human Factors, Instrumentation, and Controls: General—II

Field Programmable Gate Array-based I&C Protection System Design

Hyun-Jeong Kim, In-Seok Hwang, Seung Min Baek (KEPCO E&C)

Calculation of Fault Detection Coverage for Digital I&C Systems

Jaehyun Cho, Seung Jun Lee, Wondea Jung (KAERI)

High Spatial Resolution Reactor Power Reconstruction from External Core Distributed Measurement

Charles Stratton, Pavel Tsvetkov (TAMU)

Control Strategy Development of Advanced High Temperature Reactor System

I. Skavdahl, V. Utgikar (Univ of Idaho), Piyush Sabharwall (INL), M. Chen, X. Sun, R. N. Christensen (Ohio State Univ)

Isotopes and Radiation: General

High-Flux Accelerator-Based Neutron Source as a ²⁵²Cf Alternative

Ross Radel, Greg Piefer, Chris Seyfert, Arne Kobernik, Logan Campbell, Casey Lamers, Tye Gribb, Evan Sengbusch (Phoenix Nuclear Labs)

New Directions in Source Recoveries by OSRP at LANL

Ioana Witkowski, Anthony Nettleton, Alex Feldman (LANL)

Evaluating the Feasibility of a Simple Experiment to Validate the Existence of a Low-Energy Component to the ⁴⁰Ca(n,a)³⁷Ar Reaction Cross-Section

William H. Wilson, Steven R. Biegalski (Univ of Texas, Austin)

Validation and Uncertainty of DRF’s for a 1” X 2” NaI Collimated Detector for Radioisotope Holdup Measurements

N. Nelson, Y. Azmy, R. P. Gardner, J. Mattingly, R. Smith (NCSU), L. G. Worrall, S. Dewji (ORNL)

Innovations in Radiation Detectors: New Designs, Improvements, and Applications

Data Driven Modeling of Radiation Background using an Ensemble of Learning Methods: Initial Concepts and Preliminary Results

Miltiadis Alamaniotis, Chan K. Choi, Lefteri H. Tsoukalas (Purdue Univ)

Development of an Active Imagining Method for Examining Environmental Samples in Nuclear Safeguards

Michael Kurth, Richard Shawger, Danyal Turkoglu (Ohio State Univ), Sam Glover, Henry Spitz (Univ of Cincinnati), Lei R. Cao (Ohio State Univ)

A Quick Method to Estimate the Birks Factor for Various Scintillators

Zheng Chang (SCSU)

A New Approach in Gamma Ray Spectra Analysis: Automated Integration of Peak Detection and Spectrum Fitting using Fuzzy Logic and Multiple Linear Regression

Miltiadis Alamaniotis, Chan K. Choi, Lefteri H. Tsoukalas (Purdue Univ)

Accident Tolerant Fuel

Towards Understanding FCCI: Modeling Cerium Solid Transport in Metal Fuels

C. W. Arnold, Jack Galloway, Cetin Unal (LANL)

TRISO Coating Development for Uranium Nitride Kernels

Brian Jolly, Terrance Lindemer, Kurt Terrani (ORNL)

Uniform Corrosion of Model FeCrAl Alloys in LWR Coolants

Kurt Terrani (ORNL), Young-Jin Kim (GE Global Research Center), Bruce Pint (ORNL)

Impact of Fuel Rod Coatings on Reactor Performance and Safety

I. R. Stewart, L. F. Miller, B. D. Wirth, K. E. Sickafus (Univ of Tennessee)

Discussion of Minimum Stress Allowables for SiC Composite Cladding

Lance L. Snead, Yutai Katoh, Kurt Terrani (ORNL)

Fabrication of FeCrAl Coated Zr-alloy Fuel Cladding by Cold Spray Technique

Dong Jun Park, Hyun Gil Kim, Jeong Yong Park, Yang Il Jung, Jung Hwan Park, Yang Hyun Koo (KAERI)

Structural Materials and Advanced Measurements for Nuclear Applications

Effects of Thermal and Thermo-Mechanical Treatments on Fe-14Cr-ODS Steels Microstructure

M. Dadé, J. Malaplate (CEA), A. Deschamps (Univ Grenoble Alpes; CNRS, SIMAP)

Laser Shock Peening of Oxide-Dispersion-Strengthened Austenitic Stainless Steels

Bai Cui, Qiaofeng Lu, Dawei Li, Qing Su, Chenfei Zhang, Yongfeng Lu, Michael Nastasi (Univ of Nebraska, Lincoln)

Minor and Trace Elements in Flibe after Purification and Corrosion Testing

Michael R. Ames (MIT)

Comparison of Chemical Reactivity of CVC and CVD SiCs with UO₂

Chinthaka M. Silva, Lance L. Snead, Yutai Katoh (ORNL)

Applications of Transient Grating Spectroscopy to Radiation Materials Science

Cody A. Dennett, Michael P. Short, Sara E. Ferry, Jeffrey K. Eliason, Alexei A. Maznev, Keith A. Nelson (MIT)

Design and MCNP6 Simulation of the OSU Cryogenic Irradiation Facility

Benjamin Reinke, Thomas Blue, Brandon Wilson, Michael Eades (Ohio State Univ)

Determining Crystallographic Orientation of Material Interfaces to Gauge CRUD Resistance

Vikash K. Mishra (Univ of Arkansas), Michael P. Short (MIT)

Modeling and Simulation

Overview of the BISON Fuel Performance Code

Kyle A. Gamble, Richard L. Williamson, Shane Stafford, Giovanni Pastore, Danielle M. Perez, Jason D. Hales, Stephen R. Novascone, Russell J. Gardner, Benjamin W. Spencer (INL)

Thermal Neutron Scattering Cross Section of Beryllium Oxide

Iyad I. Al-Qasir (Univ of Sharjah)

First-Principles Study of Iodine Diffusion in Silicon Carbide

Ruixuan Han, Yingying Li, Wei Xiao (State Nuclear Power Research Institute)

Parametric Study of Flaw Detection at Liquid Metal Fast Reactor using Eddy Current Technique

Mohammad R. Quddes, Leonard J. Bond, John R. Bowler (Iowa State Univ)

Effect of Interfaces on Radiation Damage Accumulation in FeNiAl Maraging Steels

Benjamin Beeler (Univ of California, Davis; Univ of California, Berkeley), Mark Asta, Peter Hosemann (Univ of California, Berkeley), Niels Grønbech-Jensen (Univ of California, Davis)

Magnesium Oxide: A Thermal Neutron Filter

Iyad I. Al-Qasir (Univ of Sharjah)

HOGNOSE: A New Model for Corrosion in PWRs

Andrew Dykhuis, Michael P. Short (MIT)

Analysis of Creep and Mass Relocation of U-Mo/Al Dispersion Fuel

Gwan Yoon Jeong (UNIST), Yeon Soo Kim (ANL), Dong-Seong Sohn (UNIST)

A Concept for a Flexible Neutron Source

D. Wootan, K. Burns, R. Gates, G. Longoni, B. Schmitt (PNNL)

Transient Testing of Nuclear Fuels at TREAT and Other Associated Topics—I

Transient Testing Scientific Infrastructure Development to Support TREAT

Daniel M. Wachs (INL)

Status of the TREAT Reactor Restart and the Resumption of Transient Testing

John Bumgardner (INL)

Transient Testing of Nuclear Fuels in TREAT: An Overview

Arthur E. Wright (ANL)

ATF-3: An Overview of the Accident Tolerant Fuels Transient Testing Campaign in the TREAT Reactor

R. C. O’Brien, Daniel M. Wachs, A. A. Beasley (INL)

Development of Multi-Physics Methods to Support Restart of the Transient Test Reactor

Frederick N. Gleicher, Mark D. DeHart, Javier Ortensi, Yaqi Wang (INL), Anthony L. Alberti, Todd S. Palmer (Oregon State Univ)

Temperature Dependence of Test Fuel Power Density and Core Energy during Transient Reactor Test Facility (TREAT) Irradiation Experiments

Dimitrios C. Kontogeorgakos, Heather M. Connaway, Arthur E. Wright (ANL)

Transient Testing of Nuclear Fuels at TREAT and Other Associated Topics—II

TREAT Experiment Vehicle Design and Future Plans

Nicolas Woolstenhulme, C. C. Baker, John D. Bess, Cliff Davis, G. K. Housley, Colby Jensen, R. C. O’Brien, S. D. Snow (INL)

Thermal Analysis of TREAT Experimental Devices

Colby Jensen, Cliff Davis, Nicolas Woolstenhulme (INL)

TREAT Fuel Assembly Characterization for Modern Neutronics Validation Methods

John D. Bess, Mark D. DeHart (INL)

The TREAT Fast-Neutron Hodoscope and Plans for Restoring it to Operation

D. L. Chichester, S. M. Watson, J. T. Johnson, Daniel M. Wachs (INL)

Burst Behavior of Fe-Based Alloy Cladding under LOCA Conditions

Caleb Massey (ORNL, VCU), Kurt Terrani, Bruce Pint, Sebastien Dryepondt (ORNL)

Transient Testing of Nuclear Fuels at TREAT and Other Associated Topics—III–Panel

Nuclear Fuels

Study of Niobium in UO₂ Advanced Nuclear Fuel Doped with NbOx

V. Pennisi, P. Martin, P. Matheron, Ch. Riglet-Martial (CEA)

Grain Boundary Character and Fission Product Precipitation in SiC

Thomas M. Lillo, Isabella J. van Rooyen (INL), Yaqiao Wu (Boise State Univ)

An Extensive Study of LiF-ThF₄ Salt for the MSFR Fuel

E. Capelli, R. J. M. Konings (EC-JRC; Delft Univ of Technology), O. Beneš (EC-JRC)

Oxygen Potential of High Burnup UO₂

V. V. Rondinella (EC-JRC)

Fabrication of Boron-bearing UO₂ Fuel Pellet for HANARO Irradiation Test

Young Woo Rhee, Keon Sik Kim, Jae Ho Yang, Yang Hyun Koo (KAERI)

Detailed 3D Solids Dynamics of Gas-Solid Spouted Beds using Gamma Ray Computed Tomography (CT) and Radioactive Particle Tracking (RPT) Techniques

Neven Ali, Thaar Al-Juwaya, Muthanna Al-Dahhan (Missouri Univ of Science and Technology)

Current Issues in Computational Methods—Roundtable

Transport and Computational Methods

A Remez Algorithm on Finding Polar Angle Quadrature Sets for the Method of Characteristics

Yaqi Wang (INL)

Energy Efficiency of High-Performance Computing Platforms for Neutron Transport Calculations

William Boyd (MIT), Kazutomo Yoshii, Andrew Siegel (ANL)

Mathematical Methods for Hyperspectral Imaging in Landmine Detection

Ihab Makki, Rafic Younes, Clovis Frances (Lebanese Univ), Massimo Zucchetti (Politecnico di Torino)

Nuclear-pointer-based Multilevel Unionized Energy Grid Method in SuperMC2.2

Lijuan Hao, Jing Song, Liqin Hu (Chinese Academy of Sciences)

Mathematical Modeling and Uncertainty Quantification

A Backtracking Analysis Approach for Diagnostic Applications of Markov/CCMT

Jun Yang, Tunc Aldemir (Ohio State Univ)

Computational Evaluation of Station Blackout

Jack Cavaluzzi, Paul Nelson, Vera Moiseytseva (TAMU)

A Novel Coupled Computation Method for Fast Burst Reactors

Wenfeng Liang, Qilin Xie, Dong Qiu (China Academy of Engineering Physics)

Contribution of Probabilistic Approaches for the Calibration of a Fission Gas Release Model

Antoine Bouloré, Jean-Marc Martinez, Fabrice Gaudier, Christine Struzik (CEA)

Development of Multi-Level Reduced Order Modeling Methodology

Mohammad G. Abdo, Hany S. Abdel-Khalik (Purdue Univ)

Data, Analysis, and Operations for Nuclear Criticality Safety

Minimum Critical Mass of Heterogeneous Moderated Plutonium Metal Systems

A. R. Wysong, N. Glazener, R. E. Krentz-Wee, A. L. Salazar (LANL)

Benchmark Specifications and Results for Fission Density and Neutron Importance in a HEU Metal System Using ORSphere

Margaret A. Marshall, John D. Bess (INL)

Tungsten-Reflected Subcritical Measurements

J. Hutchinson, B. Richard, T. Cutler, A. Sood, M. Smith-Nelson (LANL)

MCNP6 Optimization and Testing for Criticality Safety Calculations

Forrest B. Brown (LANL)

Upper Subcritical Limit Calculations with Correlated Integral Experiments

Vladimir Sobes, Bradley T. Rearden, Don E. Mueller, William J. Marshall, John M. Scaglione, Michael E. Dunn (ORNL)

Neutron Noise Measurements on HEU Foils Moderated by Lucite

J. Hutchinson, M. Smith-Nelson, A. Sood, R. Sanchez, D. Hayes, T. Cutler (LANL), A. Chapelle, P. Casoli (CEA)

Impact of Nuclear Data Improvements on Criticality Safety Guidelines

Dustin Popp, Katherin Goluoglu, Sedat Goluoglu (Univ of Florida)

Prompt Neutron Decay Constant Determination for CFBR-II at Delayed Criticality

Lingli Song, Jiansheng Li, Haojun Zhou (CAEP)

Nuclear Fission Processes and Data–Panel

ANS 8 Standards–Forum

Nuclear Installations Safety R&D at the Department of Energy

The Department of Energy’s Nuclear Safety Research and Development Program

Alan E. Levin (DOE)

Designing an Ergonomically Sound Glovebox Glove

Cindy Lawton, Whitney Land, Jude Oka (LANL)

Stochastic Calculation of Radioactive Material Release Dose Consequences

Chad L. Pope, Kushal Bhattarai (Idaho State Univ), Jason P. Andrus (INL)

Computer Capability to Substantiate DOE-HDBK-3010 Data

David L. Y. Louie, Alexander L. Brown, Louis Restrepo (SNL)

A Test Method for Characterization of Fire Induced Uranium Aerosols

Douglas K. Clark (Y-12)

Controlled Oxidation of Tritium-Aged LaNi_4.25Al_0.75 Hydride to Support Retired Bed Disposition

G. C. Staack, M. L. Crowder, M. H. Tosten (SRNL)

Validation of Hydrogen Exchange Methodology on Molecular Sieves for Tritium Removal from Contaminated Water

G. A. Morgan (SRNL)

Nuclear Installations Safety: General

The SOARCA Surry Power Station Short-Term Station Blackout Uncertainty Analysis: MACCS Parameter Development

Nathan E. Bixler, Douglas M. Osborn, Scott Weber, Cédric J. Sallaberry, Aubrey C. Eckert-Gallup, Joseph A. Jones (SNL), S. Tina Ghosh (NRC)

Limit Surface Approach Defining Success Criteria with Uncertainties in Level 1 PSA

Douglas A. Fynan, Kwang-Il Ahn (KAERI), John C. Lee (Univ of Michigan)

Nexus Between Safety and Cyber Security–Panel

Nuclear Nonproliferation Policy: General

Nuclear Forensics: Calculation and Determining the Radioactive Sample: Kingdom of Saudi Arabia as Special Case

Salah Ud-Din Khan (King Saud Univ), Shahab Ud-Din Khan (Chinese Academy of Sciences)

A Comparison of Activation Products in Different Types of Urban Nuclear Melt Glass

Joshua Molgaard (U.S. Military Academy), John D. Auxier II, Howard L. Hall (Univ of Tennessee)

Monte Carlo Simulations of Cosmic Ray Muons for Dry Cask Monitoring

S. Chatzidakis, P. T. Forsberg, B. T. Sims, L. H. Tsoukalas (Purdue Univ)

Breaking the Barrier Between Research and Implementation–Panel

New Nuclear Construction Around the World—Status Report–Panel

Operations and Power: General

Study of the Parameters that Influence Small Modular Reactor Investment Costs

Lauren Boldon (RPI), Piyush Sabharwall (INL), Erich Schneider (Univ of Texas, Austin), Li Liu (RPI)

The Effect of PWR Size on Reactivity and Power Distribution During Reactivity Initiated Accidents

R. Busquim e Silva, A. L. F. Marques, J. J. Cruz (Univ of Sao Paulo), K. Shirvan, M. S. Kazimi (MIT)

End-of-Cycle Reactor Coolant Zinc Disappearance at Davis-Besse

John M. Riddle, Larry S. Lamanna (AREVA),Vincent N. Capozziello (FENOC)

Effects of Manual Operation during a Loss-of-Coolant Accident with Pump Unavailability

Timothy Crook, Rodolfo Vaghetto, Y. A. Hassan (TAMU)

Improving Grid Reliability Using Salt-Cooled Reactors with Air Brayton Power Cycles and Heat Storage

Charles Forsberg (MIT)

Method for Fast-Filling Fuel-Buffering System with Helium in a Pebble-bed Reactor

Hongbing Liu, Dong Du (Tsinghua Univ, Key Laboratory for Advanced Materials Processing Technology), Peng Shen (Henan Energy and Chemical Industry Group Co.)

Development of a Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using Advanced Gas-Cooled Reactor (AGR) Technology

Charles Forsberg, Joshua Richard (MIT), Justin Pounders (Univ of Mass-Lowell), Rich Kochendarfer, Kim Stein (AREVA), Eugene Shwageraus, Geoff Parks (Cambridge Univ)

Computational Tools for Radiation Protection and Shielding

Preliminary MCNPX Modeling of the F-127 Source Shipping Container for the GB-127 CO-60 Irradiator Facility

Maritza R. Gual, Pablo A. Grossi (CDTN/CNEN), Carlos A. Caballero (Radiation Consulting Group), L. C. D. Ladeira, F. S. Lameiras (CDTN/CNEN)

Production of Heavy Clusters with an Expanded Coalescence Model in CEM

Leslie M. Kerby (LANL, Univ of Idaho), Stepan G. Mashnik (LANL)

Characterization of the Neutron Detectability of Highly Enriched Uranium

G. E. McMath, T. A. Wilcox, G. W. McKinney (LANL)

A Rapid Method for Calculating K_eff Values for Spent Partitions of Radially or Axially Inhomogeneous Densities, Where Surfaces of Fuel Elements are Tapered with Porosity

E. V. Steinfelds, K. Andrew, P. Womble (Western Kentucky Univ)

Best of Radiation Protection and Shielding Division 2014—I

Computational Assessment of Naturally Occurring Background Radiation Produced by Extraterrestrial Sources

Thomas M. Miller (ORNL), Wouter C. de Wet (Univ of Tennessee), Bruce W. Patton (ORNL)

Parallel Monte Carlo Methods for Heterogeneous Hardware Computer Systems Using GPUs and Coprocessors: Recent Development of ARCHER Code

Tianyu Liu, Lin Su, Xining Du, Hui Lin, Kris Zieb, Wei Ji, Peter F. Caracappa, X. George Xu (RPI)

The Standalone Package for Enhanced Estimation of Dose Distribution

Wouter C. de Wet, Lawrence W. Townsend (Univ of Tennessee), X. George Xu (RPI), Whitney J. Smith (Univ of Tennessee)

Class II Algorithm for Charged-Particle Transport Simulation

Francesc Salvat (Univ de Barcelona)

Best of Radiation Protection and Shielding Division 2014—II

Analysis of Shutdown Dose Rate in Fusion Energy Systems Using Hybrid Monte Carlo/Deterministic Techniques

Ahmad M. Ibrahim, Douglas E. Peplow, Joshua L. Peterson, Robert E. Grove (ORNL)

Radiation Mapping at JET and ITER Using Advanced Computational Acceleration Techniques and Tools

Jonathan Naish, Frances Fox, Zamir Ghani (Culham Centre for Fusion Energy), Michael Loughlin (ITER), Lee Packer, Andrew Turner (Culham Centre for Fusion Energy)

Rigorous Two-Step Activation for Fusion Systems with PyNE

Elliott Biondo, Andrew Davis, Anthony Scopatz, Paul P. H. Wilson (Univ of Wisconsin, Madison)

Activation Neutronics for a Swiss PWR and a Swiss BWR

Manuel Pantelias, Valentyn Bykov, Benjamin Volmert (NAGRA)

Experiment Design for Secondary Particles Measurement of Helium Ions Bombarding Stopping Targets

Pi-En Tsai, Lawrence H. Heilbronn (Univ of Tennessee)

Radiation Protection and Shielding–Roundtable

ATTILA for MCNP—Tutorial

Advanced Monte Carlo Methods for Reactor Physics Analysis—I

Tally Precision Triggers for the OpenMC Monte Carlo Code

Qicang Shen (Tsinghua Univ), William Boyd, Benoit Forget, Kord Smith (MIT)

Research on On-the-fly Doppler Broadening Based on the Stochastic Sampling Algorithm

Feng Yang, Jin-Gang Liang, Gang-Lin Yu, Kan Wang (Tsinghua Univ)

Implementation of Explicit Modeling Approach in RMC Code for Stochastic Media Analysis

Shichang Liu, Ding She, Jin-Gang Liang, Kan Wang (Tsinghua Univ)

Efficient Execution of Monte Carlo Simulation Based on Pseudo-Scattering using GPU

Takuya Okubo, Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

A Case Study of the Higher-Mode Errors in Monte Carlo Source Convergence

Ding She, Zhihong Liu, Jing Zhao, Kan Wang (Tsinghua Univ)

Advanced Monte Carlo Methods for Reactor Physics Analysis—II

Implementation of Inline Equilibrium Xenon Method in RMC Code

Zonghuan Chen, Gang-Lin Yu, Jin’Gang Liang, Kan Wang (Tsinghua Univ)

Development of In-Line Temperature Dependent Cross Sections Processing Capability in RMC Code

Jiankai Yu, Jin’Gang Liang, Kan Wang (Tsinghua Univ)

HTGR Fuel Element Depletion Benchmark: Results for Infinite Fuel Pebble Lattice

Ding She, Chunlin Wei, Zhihong Liu, Shichang Liu, Kan Wang (Tsinghua Univ)

The Implementation of Modified Power Iteration Method in Continuous Energy Monte Carlo Simulation

Zhang Peng, Hyunsuk Lee, Deokjung Lee (UNIST)

Reactor Physics Design, Validation, and Operating Experience—I

Nuclear Data Sensitivity and Uncertainty Analysis for the PWR Burn-up Pin-cell Benchmark with RMC Code

Yishu Qiu, Ding She, Kan Wang (Tsinghua Univ)

Subcritical Reactivity Measurements by Neutron Source Multiplication Experiments

Lingli Song, Chun Zheng, Jinfeng Du (CAEP)

Xe-135m Impact on the PCR Measurement of CANDU6 Core

Jaeha Kim, Yonghee Kim (KAIST)

Benchmark Evaluation of HTR-PROTEUS Absorber Rod Worths (Cores 5 through 8)

John D. Bess (INL)

New Reactor Physics Benchmark Data in the March 2015 Edition of the IRPhEP Handbook

John D. Bess (INL), Jim Gulliford (OECD)

Reactor Physics Design, Validation, and Operating Experience—II

Performance Evaluation of Alternative Reflector Materials for PWRs

Jiwon Choe, Deokjung Lee (UNIST), Ho Cheol Shin (KHNP-CRI)

New Ring Type Burnable Absorber for PWRs

Jiwon Choe, Deokjung Lee (UNIST), Ho Cheol Shin (KHNP-CRI)

Improvement and Verification of Reloading Optimization Program CSA for Actual Nuclear Power Plant

Zhihong Liu, Jing Zhao (Tsinghua Univ), Xiuan Shi (China Nuclear Power Technology Research Institute)

Physics-guided Covered Mapping: A New Approach for Quantifying Experimental Coverage and Bias Scaling

Hany S. Abdel-Khalik (Purdue Univ), Ayman I. Hawari (NCSU), Congjian Wang (Purdue Univ)

Reactor Analysis Methods—I

Dynamic Simulation of Nuclear Reactors Experiencing High Rates of Deformation

Jesse Johns (Nimbus Innovations), Ville Valtavirta (VTT), Roger Lenard (Little Prairie Services Trust)

FLUENT-based Computation for a Time-Space-Dependent Neutron Kinetics Model

Dalin Zhang, Jian Ge, Wenxi Tian, Suizheng Qiu (Xi’an Jiaotong Univ)

Development of Core Sensitivity Analysis Based on Reduced-Order Modeling using Assembly Calculations

Ryota Katano, Akio Yamamoto, Tomohiro Endo (Nagoya Univ)

Convergence Analysis of Two-Node CMFD Method Applied to Neutron Diffusion Eigenvalue Problem

Yongjun Jeong, Jinsu Park (UNIST), Hyun Chul Lee (KAERI), Deokjung Lee (UNIST)

Comparison of Cross-Section Models for Functionalization and History Effect

Yunzhao Li, Shengnan Gao, Hongchun Wu, Liangzhi Cao, Yaodong He (Xi’an Jiaotong Univ)

Development of E_PGPT Surrogate Construction Capability within CRANE

Congjian Wang, Hany S. Abdel-Khalik (Purdue Univ)

Reactor Analysis Methods—II

Development of MHI FBR Nuclear Design Code System CALAXY-H/ENSEMBLE-TRIZ

Kazuki Kirimura, Yohei Kamiyama, Kazuya Yamaji, Shinya Kosaka, Hideki Matsumoto (Mitsubishi Heavy Industries), Akio Yamamoto (Nagoya Univ)

Angular Dependent Transmission Probability Method for Fast Reactor Core Transport Analysis

Akio Yamamoto (Nagoya Univ),  Kazuki Kirimura, Yohei Kamiyama, Kazuya Yamaji, Shinya Kosaka, Hideki Matsumoto (Mitsubishi Heavy Industries)

Uncertainty Quantification of Delayed Neutron Fraction of U235 Based Fuel Cores

Gérald Rimpault, David Blanchet, Jean Tommasi, Guillaume Truchet (CEA)

Advanced Equilibrium Composition Search Method for Molten Salt Breeder Reactor Based on Two-Cell Model

Yongjun Jeong, Jinsu Park, Deokjung Lee (UNIST)

Pin Power Reconstruction for PHWR Reactors Using Leakage-Corrected Discontinuity Factors

Eleodor Nichita, Elif Usalp (Univ of Ontario Institute of Technology)

Small Modular Reactors (SMRs): Reactor Physics and Fuel Cycle

Core Design Studies for a BWR-Based Small Modular Reactor with Long-Life Core

Zeyun Wu, Won Sik Yang, Shanbin Shi, Manoru Ishii (Purdue Univ)

Neutronics Simulation of Burnup-dependent Swelling of Metallic Fuel in a Linear Breed-and-Burn Fast Reactor (B&BR)

Donny Hartanto, Yonghee Kim (KAIST)

Study on Burning Strategy for Small-size Sodium-cooled Fast Reactor

Taewoo Tak, Deokjung Lee (UNIST)

Once-Through Thorium Blanket Driven to Very High Burnup by Fast Reactor Excess Neutrons

Guanheng Zhang, Massimiliano Fratoni, Jasmina Vujic, Ehud Greenspan (Univ of California, Berkeley)

Reactor Physics: General—I

Validation of the MAPTA Reactivity Monitoring Technique using a Boiling Water Reactor Turbine Trip Benchmark

Marta Nervo, Sandra Dulla, Piero Ravetto (Politecnico di Torino)

Comparative Study on Neutronics Characteristics of 1000 MWth Metal Fuel Sodium-cooled Fast Reactor

N. E. Stauff (ANL), M. M. Uematsu (JAEA), T. K. Kim (ANL)

A Mixed Spectrum Nuclear Reactor Controlled by Moderator Displacement

Neal L. Mann (Consultant)

A Comprehensive Validation Approach Using the RAVEN Code

Ivan Rinaldi (Univ of Rome), Andrea Alfonsi, Joshua Cogliatti, Cristian Rabiti (INL), Fabio Giannetti, Gianfranco Caruso (Univ of Rome)

Reactor Physics: General—II

Feasibility of Colliding Beam Fusion-Catalyzed Fast Fission Chain Reactor with Direct Conversion of Energy of Fission Fragments into Electricity and Suppressed Plutonium Production

Bogdan C. Maglich (CALSECO)

Improved Reactivity Estimation of MC²-3/DIF3D for Fast Reactor Analysis

Changho Lee, Nicolas E. Stauff (ANL)

A Novel Compact Core Design for Beam Tube Research Reactors

Zeyun Wu (NIST, Univ of Maryland), Max Carlson (MIT), Robert E. Williams, Sean O’Kelly, J. Michael Rowe (NIST)

Nuclear-Thermal Analysis of Coated Particle Dispersed Plate-Fuel Loaded in a Novel Research Reactor

Yoonhee Lee, Yonghee Kim, Nam Zin Cho (KAIST)

Isotopic Tailored Lead Coolant with New Consuming Properties for Fast Reactors

Georgy Khorasanov (National Research Nuclear Univ)

Reactor Physics: General—III

Sensitivity/Uncertainty Analysis of the Effective Delayed Neutron Fraction with Deterministic Codes

Gerardo Aliberti, Micheal A. Smith (ANL)

Application of the BigT Burnable Absorber to AP1000 First Core

Mohd-Syukri Yahya, Yonghee Kim (KAIST)

NECP-CACTI: Pressurized Water Reactor Lattice Code Development

Yunzhao Li, Chao Tian, Youqi Zheng, Hongchun Wu, Liangzhi Cao (Xi’an Jiaotong Univ)

Tutorial Series on Characterization of Uncertainty (TUSC): Reduced Order Modeling, Dimensionality, Reduction, Surrogate Modeling, Function Approximation, Fitting, etc.

Hany S. Abdel-Khalik (Purdue Univ)

LWR Fuel Reliability–Panel

Current Issues in LWR Core Design and Reactor Engineering Support–Panel

Progress in Student’s Research and Design Projects

Impact of Isotope Separation on Burnable Absorber Performance

Chidong Kong (UNIST), Ho Cheol Shin (Korea Hydro & Nuclear Power Co.), Deokjung Lee (UNIST)

Characterization of Thermal Conductivity using Deterministic Phonon Transport in Rattlesnake

Jackson R. Harter, P. Alex Greaney, Todd S. Palmer (Oregon State Univ)

Robotics and Remote Systems Topics

Performing Neutron Imaging of Mock Uranium Fuel Rods with a Robotic Manipulator

Joseph Hashem (Univ of Texas, Austin)

Strategy to Enhance Applicability of the KAERI’s Remote Response Technology

Young Choi, Kyungmin Jeong (KAERI), Inn Seock Kim (ISSA Technology)

Collaborative Robot Nuclear Surveying (CRONUS) Project

Martin Zavala, Dooroo Kim, Anna Erickson, Mark Costello (Georgia Tech)

Detection and Localization of Gamma Ray Source Using a Wireless Robot

Akanksha Singh, Shikha Prasad, Abhijit Verma (Indian Institute of Technology)

Thermal Hydraulics: General—I

Natural Convection Flow Pattern Analysis for a Large-Scaled Saltstone Facility

Si Young Lee (SRNL)

Transient Convection from Forced to Natural with Flow Reversal for CFD Validation

Blake W. Lance, Barton L. Smith (Utah State Univ)

Predicted Effects of Noncondensable Gases in a Boiling/Condensing Facility

Juan J. Carbajo (ORNL)

Steam-Water Flooding Studies at High Pressure for Severe Accident Application

K. Vierow, N. Mohammed (TAMU)

Modeling the Vitrification of Hanford Tank Waste

Donna Post Guillen (INL), Clyde J. Beers (Univ of Michigan)

CFD Benchmark Study for Modeling of Hydrogen Distribution in the Containment

F. S. Sarikurt, Y. A. Hassan (TAMU)

Desalination Applications of 10 MWe Toshiba 4S

A. Reimers, Erich Schneider, M. Flicker, M. E. Webber, J. Morton (Univ of Texas, Austin)

Thermal Hydraulics: General—II

Development, Validation, and Application of a Steam Generator Thermohydraulics Analysis Code STAF

Tenglong Cong (Xi’an Jiaotong Univ; Univ of Wisconsin, Madison), Rui Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu (Xi’an Jiaotong Univ)

A Proposed Framework for an Integration of an Experimental Apparatus to a Computational Model of a Whole Nuclear Power Plant Model for Online Feedback

Zheng Fu, Josh C. Pack, Fatih Aydogan (Univ of Idaho)

Assessment of Film Condensation Model of TRACE Code Using Reflux Condensation Test

Kyung Won Lee, Ae Ju Cheong, Andong Shin (Korea Institute of Nuclear Safety)

Study of the Diodicity of a Coned Vortex Diode

Yin Cao, Yanhua Wu, Kun Chen (Chinese Academy of Sciences)

Thermal Hydraulics: General—III

Concept for Accident Tolerant Light Water Reactor Helium Injection System

Caleb Massey, James Miller, Gokul Vasudevamurthy (VCU)

Natural Convection Shutdown Heat Removal Test Facility (NSTF) Repeatability and Project Status

D. D. Lisowski, N. C. Bremer, C. D. Gerardi, M. T. Farmer (ANL)

Containment Pressure Control Strategy Analysis for a Floating NPP

Qian Lin, Weizhong Zhang, Shengyi Si (Shanghai Nuclear Engineering Research and Design Institute)

Experimental Thermal Hydraulics

On the Characterization of a Drop-in Miniplate Experiment – Hydraulic Analysis

Wade R. Marcum, A. Weiss (Oregon State Univ), W. F. Jones, Nicolas Woolstenhulme, A. M. Phillips, K. Holdaway (INL), M. Moussaoui, P. L. Harmon, T. K. Howard (Oregon State Univ), J. Wiest, J. Campbell (INL)

On the Characterization of a Drop-in Miniplate Experiment—Structural Response Analysis

Warren Jones (INL), Wade R. Marcum, A. Weiss, T. K. Howard (Oregon State Univ), Nicolas Woolstenhulme, A. M. Phillips, J. Wiest (INL)

Experimental Results from the TAMU Air-Cooled Reactor Cavity Cooling System Experimental Test Facility

John L. Budd, Shamsul A. Sulaiman, Elvis E. Dominguez-Ontiveros, Mario Matos, Y. A. Hassan (TAMU)

The Observation of Boiling Heat Transfer Phenomenon on a Downward Facing Surface

Huai-En Hsieh, Mei-Shiue Chen, Wei-Keng Lin, Bau-Shi Pei (Tsinghua Univ)

Steam-jet DCC in Scaled Automatic Depressurization System Sparger of AP1000

Daogang Lu, Yuhao Zhang, Qiong Cao, Fenglei Niu (North China Electric Power Univ)

An Experimental Study on the Onset of Nucleate Boiling in Rectangular Channels for Downward Flow

Jung-Hyun Song, Juhyung Lee (KAIST), Soon Heung Chang (Handong Univ), Yong Hoon Jeong (KAIST)

Computational Thermal Hydraulics—I

Heat Transfer during Natural Convection between Two Rough Horizontal Parallel Plates

M. Yousaf, S. Usman (Missouri Univ of Science and Technology)

Wire-Wrapped Fuel Rod Mesh Sensitivity Study

L. M. Brockmeyer, F. S. Sarikurt, Y. A. Hassan (TAMU)

Thermal-Hydraulic Design Features of Transportable Fluoride-salt-cooled High-temperature Reactor

Chenglong Wang, Kaichao Sun, Lin-wen Hu, Suizheng Qiu, Dalin Zhang, Guanghui Su (MIT)

Development of a CFD Model for Pressure Drop Estimation of Molten Salts in a Crossflow Tube Bundle

L. B. Carasik, Y. A. Hassan, J. W. Clayton (TAMU)

Direct Numerical Simulation of Turbulent Flow in the Neat Wall Region of a Pebble Bed

L. H. Fick (TAMU), E. Merzari (ANL), Y. A. Hassan (TAMU)

Numerical Simulation of Flow and Turbulent Mixing in a T-Junction Using LES and WALE Models

Mohammed Hasan, Kaushik Das, Debashis Basu (Southwest Research Institute)

Numerical Simulations for Effects of Pipe Size on Countercurrent Flow Limitation in Slightly Inclined Pipes

Michio Murase, Yoichi Utanohara, Takayoshi Kusunoki (Institute of Nuclear Safety System, Inc.), Dirk Lucas (Helmholtz-Zentrum Dresden-Rossendorf), Akio Tomiyama (Kobe Univ)

Computational Thermal Hydraulics—II

Numerical Verification of RELAP-7 Model for a Single Phase Natural Circulation Loop

Haihua Zhao, Ling Zou, Hongbin Zhang, Richard Martineau (INL)

Core Degradation Research and the Simulation of PHEBUS FPT-1

Jun Wang (Univ of Wisconsin, Madison, Xi’an Jiaotong Univ), Michael L. Corradini, Troy Haskin (Univ of Wisconsin, Madison)

Solving Two-Phase Flow Transport Equations Using the Lax-Wendroff Scheme

Dean Wang (Univ of Mass-Lowell), John H. Mahaffy, Joseph Staudenmeier (NRC)

Analysis of Two Phase Natural Circulation Flow under IVR-ERVC using RELAP5/MOD3

Rae-Joon Park, Kwang-Soon Ha, Hwan-Yeol Kim (KAERI)

Newton-Krylov Methods in Applications of Two-Phase Flow Problems with Phase Appearance/Disappearance

Ling Zou, Haihua Zhao, Hongbin Zhang (INL)

Analysis of Two Phase Natural Circulation Flow in Core Catcher using RELAP5/MOD3

Rae-Joon Park, Kwang-Soon Ha, Hwan-Yeol Kim (KAERI)