This project proposes to develop an integral benchmark evaluation from available experimental data for zero-power tests and multi-cycle depletion for consistent and comprehensive validation of both novel high-fidelity and traditional multi-physics tools. The benchmark evaluation will be based on design, operational, and measured data from the Pressurized Water Reactor (PWR) Watts Bar Unit 1 (WB1) released by Tennessee Valley Authority (TVA). Initially this data was released for a series of benchmark progression problems developed by the Consortium for the Advanced Simulation of Light Water Reactors (CASL), a U.S. Department of Energy (DOE) Energy Innovation Hub for Reactor Modeling and Simulation (M&S) focused on developing and applying the Virtual Environment for Reactor Applications (VERA) to improve the operation and safety of Light Water Reactors (LWRs).

This proposal will develop a model of the NRX reactor and model the irradiation of a natural fuel bundle. The model will then be used to predict the release rates of chemically nonreactive gas (CNG) during nuclear fuel reprocessing.

The NRC will obtain a trial license for access to the F6/FORMOSA software, with some technical support from NC State. During this time, staff will have an evaluation period in which to develop their own interface between FORMOSA and PARCS in-house. Once the in-house interface is developed, and in combination with the temporary software license, staff should be able to demonstrate the applicability to a reasonably designed a PWR core. Once satisfied, the NRC will have the option to procure a permanent license for the ����������������as-delivered��������������� version of FORMOSA. This FORMOSA-to-PARCS combination will provide staff the means to obtain a reference PWR core without resorting to proprietary information or formal RAIs.

This proposal is to support the ExaSMR project within the Department of Energy (DOE) Exascale Computing Project (ECP). The ExaSMR project is developing capabilities to perform computational simulations of small modular reactors (SMRs) by coupling Monte Carlo neutron transport solvers to computational fluid dynamics (CFD) solvers. This proposal will develop strategies and methods to model multiphysics effects of nuclear reactors using frameworks currently being developed in the ECP.

During the first phase of CASL, the development of the VERA PWR core simulator was driven by a set of Progression Problems (PP) that defined a set of technical achievements in which code capability could be demonstrated and validated. The PPs defined the development path and priorities, and also provided a convenient task list such that CASL and DOE management could assess progress and accuracy of the methods. Following this example, we will define a set of BWR Progression Problems (BPP) to guide the work in this proposal. Each BPP will demonstrate a technical capability and a means to validate accuracy. Each BPP is actually a set of problems, not a single problem.

The Consortium for Advanced Simulation of Light Water Reactors, CASL, supports the broad national missions of enabling energy independence; supporting economic growth through the offering of superior technology ; and being good stewards of the environment, buy enabling predictive simulation of nuclear power plants. Such capability will make possible power uprates, lifetime extension and higher fuel burnups for currently operating and new Generation III+ nuclear power plants.

The Consortium for Advanced Simulation of Light Water Reactors, CASL, supports the broad national missions of enabling energy independence; supporting economic growth through the offering of superior technology ; and being good stewards of the environment, buy enabling predictive simulation of nuclear power plants. Such capability will make possible power uprates, lifetime extension and higher fuel burnups for currently operating and new Generation III+ nuclear power plants. This proposal is for work that ORNL will pay TN state takes on.