The ORIGEN MOX libraries are also compared against detailed assembly calculations from the Phase IV-B numerical MOX fuel burnup credit benchmark coordinated by the Nuclear Energy Agency within the Organization for Economic Cooperation and Development. This program included measurements of MOX fuel from a 15 Ã- 15 pressurized water reactor assembly and a 9 Ã- 9 boiling water reactor assembly. The ORIGEN libraries for MOX assembly designs are validated against destructive radiochemical assay measurements of MOX fuel from the MALIBU international experimental program. Using the SCALE depletion sequence, burnup-dependent cross sections are created for selected commercial reactor assembly designs and a representative range of reactor operating conditions, fuel enrichments, and fuel burnup.more » The burnup dependent cross sections are then interpolated to provide problem-dependent cross sections for ORIGEN, avoiding the need for time-consuming lattice physics calculations. These ORIGEN libraries are generated using two-dimensional lattice physics assembly models that include enrichment zoning and cross section data based on ENDF/B-VII.0 evaluations. In this research, ORIGEN cross section libraries for reactor-grade mixed oxide (MOX) fuel assembly designs have been developed to provide fast and accurate depletion calculations to predict nuclide inventories, radiation sources and thermal decay heat information needed in safety evaluations and safeguards verification measurements of spent nuclear fuel. (authors)ĭevelopment of ORIGEN Libraries for Mixed Oxide (MOX) Fuel Assembly Designs This paper will present an overview of the improved ORIGEN code architecture (including the methods and data structures introduced) as well as current and potential future applications utilizing the new ORIGEN framework. A recent major re-factor to the ORIGEN code architecture as part of an overall modernization of the SCALE code system has both greatly enhanced its maintainability as well as afforded several new capabilities useful for incorporating depletion analysis into other code frameworks. The ORIGEN package serves as the core depletion and decay calculation module within the SCALE code system. This work presents a description of the initial integration of ORIGEN in PROTEUS, mainly performed during FY 2015, with minor updates in FY 2016.« lessĭevelopment of an object-oriented ORIGEN for advanced nuclear fuel modeling applications Recently, ORIGEN has received considerablemore » modernization to provide the high-performance depletion/decay capability within the NEAMS toolkit. The scalability and mesh generality enable the transfer of neutron and power distributions to other codes in the NEAMS toolkit for advanced multiphysics analysis. PROTEUS’s key capability is the efficient and scalable (up to hundreds of thousands of cores) neutron transport solver on general, unstructured, three-dimensional finite-element-type meshes. The US Department of Energy’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program has contributed significantly to the development of the PROTEUS neutron transport code at Argonne National Laboratory and to the Oak Ridge Isotope Generation and Depletion Code ( ORIGEN) depletion/decay code at Oak Ridge National Laboratory. Because of the improved mod system you are able to install the new content easily and automatically.Status Report on NEAMS PROTEUS/ ORIGEN Integration If the variety of machinery does not meet your needs, you can download plenty of vehicles, equipment and other modifications from the Internet. Thanks to the cooperation and official license of Kässbohrer you take control of authentic Pistenbully snow groomers. Through several activities you build up financial resources allowing you to buy better equipment. In the career mode you enter a unique and large winter landscape and experience the workaday life in the swiss alps in a completely adapted and freely accessible world. The "Ski Region Simulator Gold Edition" contains plenty of features and possibilities:
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