Physor2010

Full papers submitted to PHYSOR-2010 will be channeled for review into the following 14 technical tracks, which will include both general and special sessions. A selection of the best papers will be published in a special issue of Nuclear Science and Engineering, the international research journal of the American Nuclear Society. The technical topics assigned to each track are summarized below.

Track 1	Nuclear Data Measurements, evaluations, validation, covariance data, and data needs. A partial list of potential topics of interest in this track includes: Nuclear Data Measurements Cross Section Evaluations & Libraries Nuclear Data Testing & Validation Covariance Data
Track 2	Deterministic Transport Theory This track comprises deterministic methods and algorithms for solving the neutral-particle transport equation with particular focus on reactor physics applications. A partial list of potential topics of interest in this track includes: Numerical methods for deterministic transport Iterative acceleration of deterministic transport methods Hybrid methods for neutron transport High performance computing for deterministic transport Analytical/numerical transport benchmarks Verification and validation for transport methods Deterministic transport methods on unstructured grids Transport in stochastic media Charged particle transport Special sessions Advances in Neutron Flux and Fluence Calculational Methods - Ali Haghighat (University of Florida) and Ren-Tai Chiang (AREVA)
Track 3	Monte Carlo Methods Development and application of stochastic methods and codes. A partial list of potential topics of interest in this track includes: Monte Carlo source convergence acceleration, issues and applications Monte Carlo depletion and propogation of uncertainty Sensitivity calculations using Monte Carlo codes Monte Carlo versus deterministic codes for safety and design assessment Monte Carlo methods - general Monte Carlo variance reduction methods
Track 4	Reactor Analysis and Optimization Lattice physics, cross-section libraries, advances in methods in reactor statistic and kinetics, homogenization and nodal methods, pin power reconstruction methods, depletion methods, in-core fuel management and optimization, core monitoring, and high-performance computing in reactor physics. A partial list of potential topics of interest in this track includes: Reactor Analysis Methods Lattice Physics Methods & Validation Homogenization & Nodal Methods Pin Power Reconstruction Methods In-Core Fuel Management and Optimization High-Performance Computing in Reactor Physics Special sessions 3-D Depletion using Transport Methods - Glenn E Sjoden (University of Florida) Special Session in Memory of Rudi Stamm'ler - Charles Wemple (Studsvik), TK Kim (ANL), Tomasz Kozlowski (KTH)
Track 5	Reactor Design and Operation Improvements in fuel assembly and reactor designs, improvement in fuel assembly and reactor design to operate fuel failure free, light and heavy-water reactor designs, gas-cooled reactor designs, fast reactor designs, space nuclear power & propulsion. A partial list of potential topics of interest in this track includes: Light-Water Reactor Design & Analysis Heavy-Water Reactor Design & Analysis Fast Reactor Design & Analysis Gas-Cooled Reactor Design & Analysis Advanced Reactor Designs Reactor Operation and Control Core Monitoring Space Nuclear Power & Propulsion Deep Burn I and II
Track 6	Nuclear Fuel Cycle Fuel cycle physics, fuel cycle design optimization, strategies for plutonium management and minor actinide reduction, strategies to close the fuel cycle, developments in enrichment and reprocessing facilities, fuel cycle services globalization.The list of potential topics of interest includes: Current status of the nuclear fuel cycle worldwide: technology, policy and socio-economical aspects Advancements in the front-end fuel cycle technologies Solutions and challenges at the fuel cycle back end Design, analysis and optimization methods for fuel cycles, coupling of neutron transport and transmutation models Experimental programs in support of advanced fuel cycles, advanced fuel development Plutonium management The role of Thorium fuel cycle in sustainable nuclear energy future Transuranic actinide managements Fission product management LWRs, CANDU, HTRs, and fast reactors in fuel cycle scenarios Deep burn reactor-based approaches towards environmentally benign nuclear energy CANDLE & Traveling-Wave and Other Advanced Burnup/Fuel Management Approaches Hybrid systems for energy production and nuclear waste minimization Potential fuel cycle scenarios for nuclear energy future as sustainable energy source Globalization of the nuclear fuel cycle: non-proliferation challenges, resource management, etc. Uncertainty quantification in fuel cycle analysis Benchmark efforts in support of fuel cycle studies Advanced fuel cycle and related nuclear system concepts Other topics related to fuel cycle advancements
Track 7	Nuclear Criticality Safety Analysis methodologies, experiments, burnup credit, spent fuel disposition. A partial list of potential topics of interest in this track includes: Nuclear Criticality Safety Burnup Credit Nuclear Criticality Safety Benchmarks Spent Fuel Disposition
Track 8	Transient, Safety Analysis and Thermal Hydraulics Advances in multi-physics and multi-scale modeling, best-estimate safety analysis, thermal hydraulics, 3D coupled neutronics/thermal hydraulics, probabilistic risk assessment, severe accident analysis and mitigation. A partial list of potential topics of interest in this track includes: 3D Transient Analysis Methods Multi-Physics Reactor Simulations Developments in Probabilistic Risk Assessments Severe Accident Analysis and Mitigation Reactor thermal hydraulics
Track 9	Research Reactors and Spallation Sources Design and applications of medium & high flux research reactor, Characteristics and applications of neutron spallation source. A partial list of potential topics of interest in this track includes: Applications of research reactors Design features of (recently commissioned or under construction) research reactors Physics test at research reactors Code validation calculations on research reactors Nuclear characteristics of medium and high flux research reactors (e.g. thermal to fast flux ratio for the neutron transmutation doping) International cooperation regarding the utilization of research reactors Accelerator and Spallation Physics
Track 10	Integral Experiments and Facilities for Safety Research Zero-power reactor experiments, measurement techniques, interpretation and analysis, design, utilization of large thermal-hydraulics & irradiation facilities. A partial list of potential topics of interest in this track includes: Integral Experiments and Analysis Reactor Physics Benchmarks Capabilities of Experimental Facilities
Track 11	Verification, Validation and Uncertainty Analysis ANS standards, NEA benchmarks, sensitivity and uncertainty analysis, verification and validation methodologies and studies. A partial list of potential topics of interest in this track includes: Reactor Physics Standards Verification & Validation Methods Sensitivity/Uncertainty Analysis
Track 12	Fuel, Materials and Mechanical Analysis Modeling of fuel and cladding behavior, experimental tests, material and mechanical analysis, spent fuel performance, fuel manufacturing, challenges to extend burnup and enrichment limits, development of new burnable absorbers, developments in PIE techniques. A partial list of potential topics of interest in this track includes: Fuel & Materials Behavior Fuel Performance Models Challenges to Extend Burnup and Enrichment Limits
Track 13	Radiation Applications and Nuclear Safeguards Radiation protection, applications of radioisotopes and radiation, computational medical physics, nuclear techniques for non-proliferation, nuclear techniques for homeland security. A partial list of potential topics of interest in this track includes: Radiation Protection Medical Physics Applications Nuclear Techniques for Non-Proliferation Nuclear Techniques for Homeland Security Special sessions Computational Medical Physics - Glenn E Sjoden (University of Florida)
Track 14	Nuclear Power and Sustainable Development Criteria for increased sustainability of nuclear power, needed measures (short, medium, long term), process heat and hydrogen generation, education, and training needs, infrastructure needs to support the nuclear renaissance. A partial list of potential topics of interest in this track includes: Nuclear Power & Sustainable Development Process Heat and Hydrogen Generation Infrastructure Needs to Support the Nuclear Renaissance Special sessions Reactor Physics Education & Training Needs (Panel)