This proposal is a request to be eligible to participate in DOE's Fellowship and Scholarship Support program where NE eligible students can apply for scholarships and fellowships per the Funding Opportunity Announcement. This is up to a 10 year cooperative agreement program and may run up to 13 years to accredited US Colleges and Universities for the US Department of Energy's Office of Nuclear Energy Fellowship and Scholarship Awards.������������������

NCSU will use the German HTGR source term analysis code STACY to calculate failure fractions and fractional radionuclide releases from the TRISO particles and fuel pebbles for selected irradiation and heating conditions. X-energy will compare these results with those obtained by their proprietary code XSTERM, as a means of code verification.

The Necsa has granted funds to to carry out research activities in the field of development and coupling COBRA-TF code version for research and power reactors. This grant will provide general support, guidance and training with regard to the establishment of an independent power reactor calculation capability at Necsa. The NCSU will continue to develop the COBRA-TF code system and shall provide Necsa with updates as available. This agreement then enables a cost free, non-commercial use of the multi-user license of COBRA-TF at Necsa.

Joint Faculty Appointment with BEA

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).

20% of Dr. Kautz���s salary will be provided by the Pacific Northwest National Laboratory (PNNL) to capture her effort on research at PNNL. Dr. Kautz���s joint appointment will provide a formal agreement for Dr. Kautz to conduct research in PNNL and to facilitate collaboration between PNNL and North Carolina State University.

Input to the Preliminary PIRT report: meeting participation, design familiarization, identification, description and ranking of candidate limiting design-basis events with respect to phenomena, assessment and ranking of state of knowledge of identified phenomena

The goal of the proposed project is to develop an integral benchmark evaluation based on available experimental data from cold ramp tests performed at the Studsvik testing R2 reactor. Such transient multi-physics benchmark evaluations are needed to support the U.S. DOE Nuclear Energy (NE) such as Fuel Cycle Technologies (FCT), LWR Sustainability (LWRS), and Advanced Modeling and Simulation (AMS) programs for validation of the NEAMS ToolKit and the VERA suite. Evaluation of transient multi-physics experimental data for LWR systems is a growing area of interest for U.S. DOE. Analyses of reactivity-initiated accidents such as design basis accidents as well as the slower and less severe anticipated operating occurrences (AOOs) are important in determining the overall safety of the current fleet and future nuclear power plants. Industry challenge problems, as the pellet cladding interaction (PCI) and the pellet cladding mechanical interaction (PCMI), are associated with those events. PCI and PCMI are based on multi-physics and multi-scale phenomena requiring accurate and realistic modeling and simulation. Three-dimensional fuel performance models coupled with reactor physics and thermal-hydraulics models are needed to assess the complex coupled physics and irregular geometries responsible for PCI/PCMI fuel failures. At present time, there is a need for adequate high-quality experimental data for PCI/PCMI industry challenge problems to properly validate both the existing multi-physics tools and as well as the high-fidelity multi-physics code systems being developed. The proposed project will address this need by evaluating test reactor data from controlled experimentation. The selected cold ramp tests were performed in 2005 and were experimental simulations of an uncontrolled withdrawal of a control rod group in a cold critical LWR which is a reactivity transient representative of AOOs. These special cold ramp tests were selected to: (1) develop a case problem based on measurements that involve two or more physical phenomena; and (2) investigate PCMI phenomenon in fuel rods. The selected dynamic/transient tests are multi-physics by nature: involve transient changes and interactions between reactor physics, thermal-hydraulics, and fuel performance. Multi-physics benchmark specifications will be developed to provide the data necessary to construct calculation models. The IRPhEP guidelines will be extended to make the evaluation process applicable for multi-physics transients. All available R2 reactor information, related to the initial conditions and transient tests, will be utilized. The information will constitute the Benchmark Experiment Data. This data will be subjected to Benchmark Evaluation Process. Based on the lessons learnt during the preparation of the benchmark specifications and its execution, a proposal for developing a multi-physics and transient evaluation protocol will be prepared using similar review pathway and similar evaluation format as the one established in IRPhEP: collecting benchmark experimental data, follow-up benchmark evaluation process, and peer review.

Dr. Bolotnov will apply his expertise, knowledge and experience in as one of the leaders in the area of high resolution simulation of reactor flows to contribute to relevant projects conducted at ORNL. It is estimated that Dr. Bolotnov will spend about 40% of his academic time on those activities to support and enhance research capabilities at the Oak Ridge National Laboratory.

The scope of this work package to develop an uncertainty / sensitivity methodology for Xe-100 equilibrium core analysis and apply it to VSOP99 best estimate model. The methodology includes identifying the most important parameters in the VSOP99 model including the multi-group constants and propagating the uncertainties to the selected Figures of Merit (FOMs).