FUMAC—A New Model for Light Water Reactor Fuel Relocation and Pellet-Cladding Interaction

Walton, Lewis A.; Matheson, J.E.

doi:10.13182/nt84-a33336

Cited by 10 publications

(4 citation statements)

References 3 publications

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“…As more fragments are formed which are increasingly smaller, the propensity for axial relocation increases. To determine the number of fragments in the fuel, calculations are performed based on models by Coindreau [42], Walton [43], and Barani [44] which relate to the size of these fragments. These calculations are then used to inform the axial relocation model of the characteristic size of these fragments for a mass packing calculation.…”

Section: A212 Fuel Fragmentation and Pulverizationmentioning

confidence: 99%

NEAMS Burnup Extension Accomplishments and Remaining Modeling Gaps

Capps,

Greenquist,

Schappel

et al. 2024

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Section: A212 Fuel Fragmentation and Pulverizationmentioning

confidence: 99%

NEAMS Burnup Extension Accomplishments and Remaining Modeling Gaps

Capps,

Greenquist,

Schappel

et al. 2024

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“…and WALTON [52]. The details for these models can be found on the BISON documentation page [38] or in their respective references.…”

Section: Fragment and Pulver Shapementioning

confidence: 99%

“…In all cases, the number of fragments is a function of the peak power observed. For the COINDREAU [12] and WALTON [52], a burnup dependence is also introduced resulting in more cracking and irradiation progresses.…”

Section: Fragment and Pulver Shapementioning

confidence: 99%

BISON Fuel Fragmentation Relocation and Dispersal (FFRD) Assessment Database for Eventual Use in Bayesian Calibration

Gamble

2023

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Existing light-water reactor (LWR) fuel vendors have been interested in seeking increased discharge burnups of nuclear fuel rods for improved economics for quite a few years. With increased burnups come additional challenges that must be addressed. It has been experimentally observed that average burnups higher than the current regulatory limit of 62 MWd/kgU may undergo fuel fragmentation, relocation, and dispersal (FFRD) during a loss-of-coolant accident (LOCA). Industry must demonstrate approaches to mitigate FFRD. In an effort to support industry, the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program within the U.S. Department of Energy (DOE) has for several years invested in developing multiscale models and creating a validation/assessment database for these models to study the mechanisms driving FFRD. This report provides an update on changes made to the assessment database and new models added to BISON to support the study of fuel rod behavior during FFRD. An effort has been initiated this year to begin adding dedicated inputs to the publicly available Virtual Test Bed (VTB) repository for industry use. A section of this report details the efforts made in this area. NEAMS has recently developed new capabilities in the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework's stochastic tools module for calibration using Bayesian inference. The goal in the future is to use these capabilities to calibrate and identify weaknesses in the existing BISON models for FFRD. The report concludes with a discussion on the models most likely to benefit the most from such calibration. iv

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“…The relocation of fragments and the relaxation of both stresses and strains are usually separately modeled. The relocation of fragments can be treated only on an empirical way (Oguma, 1983;Walton and Matheson, 1984;Ito et al, 1983). The relaxation of stresses and strains can be treated through the mechanical laws by considering the fragmentation using a material approach (Ito et al, 1983;Jankus and Weeks, 1972;Rashid, 1974;Williford et al, 1982;Riktzhaupt-Kleissl and Heck, 1993;Garcia et al, 2002) or an inelastic strain approach (Jernkvist, 1997;Marino et al, 1996;Harriague et al, 1980;Lassmann and Moreno, 1977).…”

Section: Introductionmentioning

confidence: 99%