BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented Simulation Environment (MOOSE) finite element library. One of its major goals is to have a great amount ...

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2020.1836940

BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms

A new high-fidelity neutronics code NECP-X

The Virtual Environment for Reactor Applications (VERA): Design and architecture☆

This paper describes the methodology developed and implemented in the Virtual Environment for Reactor Applications Core Simulator (VERA-CS) to perform high-fidelity, pressurized water reactor (PWR), multicycle, core physics calculations. Depletion of the core with pin-resolved power and nuclide detail is a significant advance in the state of the art for reactor analysis, providing the level of detail necessary to address the problems of the U.S. Department of Energy Nuclear Reactor Simulation Hub, the Consortium for Advanced Simulation of Light Water Reactors (CASL). VERA-CS has three main components: the neutronics solver MPACT, the thermal-hydraulic (T-H) solver COBRA-TF (CTF), and the nuclide transmutation solver ORIGEN. This paper focuses on MPACT and provides an overview of the resonance self-shielding methods, macroscopic-cross-section calculation, two-dimensional/one-dimensional (2-D/1-D) transport, nuclide depletion, T-H feedback, and other supporting methods representing a minimal set of the capa...

VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion

High burnup fuel fragmentation, relocation, and dispersal is one of the largest hurdles for the nuclear industry to clear before rod average burnup can be increased beyond 62 GWd/MTU. This objective of this work is to inform the high burnup loss-of-coolant-accident (LOCA) safety case for a core containing high burnup fuel to help accelerate the nuclear industry’s goals to (1) extend cycle lengths to 24 months and (2) increase peak rod average burnup to 75 GWd/MTU. The results of this analysis will define realistic, prototypic LOCA conditions to design subsequent separate effects and integral testing and will inform advanced modeling and simulation to develop mechanistic models. US Department of Energy tools were used to evaluate commercial pressurized water reactor (PWR) fuel susceptible to fragmentation under high burnup conditions. Realistic, rather than bounding, 24-month core designs and operating conditions (power history, axial profile, thermal boundary condition, flux, etc.) for VERA depletion analyses were provided by an industry partner. RELAP5-3D provided LOCA transient conditions (decay heat, thermal hydraulic conditions, etc.) for a core containing high burnup fuel (i.e., over 62 GWd/MTU with peak rod being 75 GWd/MTU). These operating conditions were entered into BISON to evaluate the evolution of the high burnup fuel under steady-state and transient conditions. BISON was used to determine the limiting fuel rod in each high burnup assembly and to evaluate the impact of pretransient fuel conditions (i.e., radial temperature profile), clad strain, ballooning behavior, and burst timing on the fuel’s susceptibility to high burnup fuel fragmentation. These efforts culminated in this summary of the potential impacts of high burnup fuel fragmentation, relocation, and dispersal and definition of prototypic LOCA conditions.

Full core LOCA safety analysis for a PWR containing high burnup fuel

Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT

/pdf/mpact-theory-manual-version-2-2-0-3alhymt408.pdf

MPACT Theory Manual, Version 2.2.0

As part of ongoing work with Consortium for Advanced Simulation of Light Water Reactors (CASL), the 2D/1D code, DeCART, has demonstrated some of the advantages of the 2D/1D method with respect to realistic, full-core analysis, particularly over explicit 3D transport methods, which generally have higher memory and computation requirements. The 2D/1D method performs 2D-radial transport sweeps coupled with ID-axial diffusion calculations to provide a full 3D simulation. DeCART employs the 2D method of characteristics for the radial sweeps and ID one-node nodal diffusion for the axial sweeps, coupling the two methods with transverse leakages to ensure a more consistent representation of the transport equation. It has been observed that refinement of the axial plane thickness leads to instabilities in the calculation scheme. This work assesses the sources of these instabilities and the approaches to improve them, especially with respect to negative scattering cross sections and the tightness of the 2D-radial/ID-axial coupling schemes. Fourier analyses show that the existing iteration scheme is not unconditionally stable, suggesting a tighter coupling scheme is required. For this reason 3D-CMFD has been implemented, among other developments, to ensure more stable calculation. A matrix of test cases has been used to assess the convergence, with themore » primary parameter being the axial plane thickness, which has been refined down to 1 cm. These cases demonstrate the issues observed and how the modification improve the stability. However, it is apparent that more work is necessary to ensure unconditional stability. (authors)« less

Assessment and improvement of the 2D/1D method stability in DeCART

2-D/3-D coupling between the method of characteristics and discrete ordinates

/pdf/mpact-vera-input-user-s-manual-version-2-2-0-1daq9s2ubf.pdf

MPACT VERA Input User s Manual, Version 2.2.0

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