The AMP (Advanced MultiPhysics) Nuclear Fuel Performance code

Clarno, Kevin T.; Philip, Bobby; Cochran, William K.; Sampath, Rahul S.; Allu, Srikanth; Barai, Pallab; Simunovic, Srdjan; Berrill, M.; Ott, L.J.; Pannala, Sreekanth; Dilts, Gary A.; Mihaila, Bogdan; Yesilyurt, Gokhan; Lee, Jung Ho; Banfield, James

doi:10.1016/j.nucengdes.2012.07.018

Cited by 22 publications

(11 citation statements)

References 16 publications

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“…The cross sections used by the SP N equations are generated by the XSProc module of the SCALE package [21]. The heat transfer and subchannel equations are solved using the Advanced Multiphysics (AMP) package [42,43]. The heat transfer equation is discretized using standard trilinear continuous Galerkin finite elements and the subchannel equations employ a finite difference approximation [18].…”

Section: Resultsmentioning

confidence: 99%

An assessment of coupling algorithms for nuclear reactor core physics simulations

Hamilton

Berrill

Clarno

et al. 2016

Journal of Computational Physics

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This paper evaluates the performance of multiphysics coupling algorithms applied to a light water nuclear reactor core simulation. The simulation couples the k-eigenvalue form of the neutron transport equation with heat conduction and subchannel flow equations. We compare Picard iteration (block Gauss-Seidel) to Anderson acceleration and multiple variants of preconditioned Jacobian-free Newton-Krylov (JFNK). The performance of the methods are evaluated over a range of energy group structures and core power levels. A novel physics-based approximation to a Jacobian-vector product has been developed to mitigate the impact of expensive on-line cross section processing steps. Numerical simulations demonstrating the efficiency

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Section: Resultsmentioning

confidence: 99%

An assessment of coupling algorithms for nuclear reactor core physics simulations

Hamilton

Berrill

Clarno

et al. 2016

Journal of Computational Physics

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“…The multi-species capability of the AMP nuclear fuel code [2] is intended to allow the modeling of radiationdriven redistribution of various elements through solid metal nuclear reactor fuels. The initial model AMP provides for U-Pu-Zr fuels is based on the analysis of the Integral Fast Reactor (IFR) fuel development program experiment X419 post-irradiation data described in [1], referred to here as the KHHS model.…”

Section: Model Descriptionmentioning

confidence: 99%

Multispecies Diffusion Capability For The AMP Nuclear Fuel Performance Code (LANL Milestone M31MS060301 Final Report)

Dilts¹

2012

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This work addresses only diffusion. The contact solver in AMP was not sufficiently developed this year to attempt treatment of species contact. A cylindrical tensor diffusion coefficient model was added to the AMP code, with the KHHS model [1] implemented into the AMP material library as a specific example. A cylindrical tensor diffusion operator manufactured solution verification example was coded. Before meeting the full text of the milestone task, it remains to: (1) code and run a cylindrical tensor diffusion solver manufactured solution (2) code and run the validation example of [1] (3) document results. These are dependent on developing new capabilities for the AMP code requiring close collaboration with the AMP team at ORNL. The model implemented provides a good intermediate first step toward a general multispecies solver.

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“…These external factors exist in the form of the power distribution, coolant conditions (temperature and pressure), mechanical stresses (debris, bowing, and fretting), and chemistry effects (oxidation and CRUD). This report documents the initial developments in the Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) [4] to incorporate an improved predictive nuclear fuel assembly modeling capability that accurately accounts for science domains that are beyond a single, isolated pin and traditionally modeled as source-terms or boundary conditions. Early work has focused on incorporating a physics-based detailed power distribution by leveraging the radiation transport capability from Scale/Denovo (Denovo) [6].…”

Section: Introductionmentioning

confidence: 99%

Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

Clarno¹,

Hamilton²,

Philip³

et al. 2012

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The AMP (Advanced MultiPhysics) Nuclear Fuel Performance code

Cited by 22 publications

References 16 publications

An assessment of coupling algorithms for nuclear reactor core physics simulations

An assessment of coupling algorithms for nuclear reactor core physics simulations

Multispecies Diffusion Capability For The AMP Nuclear Fuel Performance Code (LANL Milestone M31MS060301 Final Report)

Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

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