Hello, A yearly allocation for the LCRC cluster has been requested with the following updated information: Submitter/PI: Justin W. Thomas Project Name: SHARP_ARC Division: NE, MCS Project title: Multi-physics Simulation of SFR Core Radial Expansion with SHARP Associated funding: DOE-NE Advanced Reactor Concepts Other Systems: NE Division clusters, MCS Cosmea cluster Science: Following multi-year efforts for development of coupled neutronics, computational fluid dynamics (CFD), and computational structural mechanics (CSM) analysis capabilities, the SHARP multi-physics nuclear reactor analysis toolkit was released for distribution (via an end-user license agreement) at the end of March 2016. In FY17, our main focus will therefore shift toward testing, validation and verification of SHARP component codes and multi-physics toolkit in application to challenge problems for advanced reactor designs. The objective is to assess SHARP capabilities in addressing the high-fidelity modeling and simulation needs that have been identified as important to customers in the nuclear industry and other DOE R&D programs (particularly the Advanced Reactor Technologies program). One challenge problem that has been identified is the need to assess hot pin/hot channel factors for sodium-cooled fast reactor designs. Hot pin and hot channel factors are a means of accounting for deviations between the actual manufactured nuclear fuel pins and the design specifications, as well as deviations in the actual operating flow conditions from the idealized flow field assumed for design calculations. In this effort, SHARP will be used to explicitly model the standard assumptions made in conservative analyses by reassessing hot-channel and hot-pin factors for Argonne’s AFR-100 reactor concept. The fuel assembly with peak power-to-flow ratio, and the peak-to-average pin power, temperature and flow distributions within that fuel assembly under nominal conditions will be identified. The impact of inlet flow maldistribution and resulting temperature variations, cladding circumferential temperature variation, uncertainties and tolerances in fuel manufacturing, core lo ading errors, and uncertainties in heat transfer correlations will also be assessed. If successful, reliable prediction of these factors will enhance the safety margins and therefore improve the economic competitiveness of new reactor concepts. A second challenge problem is to demonstrate “SHARP Zoom”, a multi-scale modeling capability for a focused view of a select region of an otherwise homogenized core model. The “SHARP Zoom” concept is a multi-scale modeling technique aimed to achieve a high-fidelity (focused) view of a select zone (i.e., fuel assembly) as part of a homogenized whole-core analysis to reduce the computational requirements and cost significantly in comparison to a full-core pin-by-pin analysis. Further, the allocation will be used to support international collaborations for code validation activities. The first is a U.S.-Japan Bilateral collaboration on sodium-cooled fast reactor technology development. For the advanced modeling & simulation task under the U.S.-Japan Bilateral Commission on Civil Nuclear Cooperation, benchmark simulation of a sodium experiment using wire-wrapped 37-pin bundles from JAEA’s Plant Dynamic Test Loop facility will be pursued to validate SHARP CFD solvers for liquid metal coolants. Under a collaboration between the U.S. and European Union, there are tasks earmarked for further SHARP CFD validation, including exercises related to flow in wire-wrapped fuel assemblies, and validation of approaches that couple conventional 1-D codes with 3-D CFD. Project description: As the SHARP modeling and simulation toolkit is maturing, the focus is on customer-oriented applications and further validation exercises. This allocation will help with those applications, for performing small to moderate scale simulations and for scaling up to ALCF. The SHARP toolkit is regularly compiled on Blues using Intel or GNU compilers. The components of SHARP—the Nek5000 computational fluid dynamics code and the PROTEUS neutron transport code—have already been demonstrated to scale well not only on Blues but on Blue Gene/P. This project will be used by 4-5 analysts in the NE and MCS Divisions. Industry partnership: Project URL: http://energy.gov/ne/advanced-modeling-simulation/advanced-nuclear-reactors Current FY Hours Used: undetermined amount New FY Requested allocation: 1000000 Q1: 250000 Q2: 250000 Q3: 250000 Q4: 250000 Justification: FY17 efforts for SHARP are highly focused on solving challenge problems for customers and code validation. FY16 efforts were focused on code development, as there was a major release, and so computational requirements were lower than usual. If the project is successful, we anticipate that FY17 and beyond will be highly resource intensive. The components of SHARP—the Nek5000 computational fluid dynamics code and the PROTEUS neutron transport code—have already been demonstrated to scale well not only on Fusion but on Blue Gene/P. Nek5000 has demonstrated > 80% parallel efficiency on BG/P (strong scaling) out to P=131,072 processors, using only 7300 points/processor at the largest scale. PROTEUS has demonstrated greater than 90% strong space-angle scaling at the 100,000 processer level and was nominated for the Gordon Bell Prize for its parallel performance. Storage requirements: 4 TB would provide convenience, considering the relatively large number of collaborators working simultaneously. Thank You, The LCRC Accounts System