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DOE OSTI · 3013447

Operational Reactor Depletion Analysis Capability

Abstract

The milestone for the operational reactor depletion demonstrates a cycle depletion simulation of Watt's Bar Unit 1 Cycle 1. The simulation was performed using the VERA-CS components MPACT and COBRA-TF. The simulation was performed on the Titan and Eos machines at the Oak Ridge Leadership Computing Facility. The simulation results include the critical boron concentration, the pin resolved power, temperature, and fluid density distributions, and detector responses as a function of time. These results are presented and the critical boron concentration is compared with measured data. The comparison is reasonable given the modeling approximation used at this point. Several suggestions, both near and longer term, are given for areas of future work which include improving the methods, data, models, and computational performance. For those solution results which are not compared to measurement, e.g. power and temperature distributions, their behavior coincides with analysts' expectations. An important next step in the validation of VERA-CS will be the comparison of the computational results to the measured flux data. To satisfy this L1 milestone, numerous capabilities were successfully added as a part of supporting L2 and L3 milestones. These include: full core depletion, generation of a new cross section library, coupling of neutronics and thermal hydraulic feedback, and detector response modeling. In addition to the operational reactor depletion, several 2-D core parametric studies were performed to assess the new simulation capability and to develop guidelines on model approximations and discretizations. Some of the conclusions from these studies are: • The simulation of B-10 depletion in the coolant is necessary to accurately predict critical boron concentrations, • If the end of cycle state is of primary interest in the simulation, then significant approximations may be made in the cycle history. The ability to make use of this approximation without a notable loss in accuracy will considerably accelerate multi-cycle analysis, • The new 47-group cross section library with a transport correction of the P 0 scattering can provide solutions very efficiently and which are nearly as accurate as solutions generated with explicit P 2 scattering, and • Simplified modeling of the equilibrium xenon concentration is well predicted by the existing depletion solver, and only in certain circumstances (e.g. large and "instantaneous" changes to rod position or T/H conditions) would an explicit physical model need to be included. Overall the milestone is considered a success as the objectives were met and several new and important results were produced from this work. The results and conclusions of this milestone will continue to guide future work and become the basis for addressing the CASL Challenge Problems.

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BibTeXRIS

Kochunas, Brendan, Graham, Aaron, Jabaay, Daniel, Stimpson, Shane, Downar, Thomas, Collins, Benjamin, Kim, Kang Seog, Wieselquist, William, Salko, Robert. 2014-09-30. Operational Reactor Depletion Analysis Capability. https://doi.org/10.2172/3013447

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