Progress toward Monte Carlo-thermal hydraulic coupling using low-order nonlinear diffusion acceleration methods

A new approach for coupled Monte Carlo (MC) and thermal hydraulics (TH) simulations is proposed using low-order nonlinear diffusion acceleration methods. This approach uses new features such as coarse mesh finite difference diffusion (CMFD), multipole representation for fuel temperature feedback on...

Full description

Bibliographic Details
Main Authors: Herman, Bryan R (Contributor), Forget, Benoit Robert Yves (Contributor), Smith, Kord S. (Contributor)
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering (Contributor)
Format: Article
Language:English
Published: Elsevier, 2017-11-16T16:44:53Z.
Subjects:
Online Access:Get fulltext
LEADER 02013 am a22002053u 4500
001 112202
042 |a dc 
100 1 0 |a Herman, Bryan R  |e author 
100 1 0 |a Massachusetts Institute of Technology. Department of Nuclear Science and Engineering  |e contributor 
100 1 0 |a Herman, Bryan R  |e contributor 
100 1 0 |a Forget, Benoit Robert Yves  |e contributor 
100 1 0 |a Smith, Kord S.  |e contributor 
700 1 0 |a Forget, Benoit Robert Yves  |e author 
700 1 0 |a Smith, Kord S.  |e author 
245 0 0 |a Progress toward Monte Carlo-thermal hydraulic coupling using low-order nonlinear diffusion acceleration methods 
260 |b Elsevier,   |c 2017-11-16T16:44:53Z. 
856 |z Get fulltext  |u http://hdl.handle.net/1721.1/112202 
520 |a A new approach for coupled Monte Carlo (MC) and thermal hydraulics (TH) simulations is proposed using low-order nonlinear diffusion acceleration methods. This approach uses new features such as coarse mesh finite difference diffusion (CMFD), multipole representation for fuel temperature feedback on microscopic cross sections, and support vector machine learning algorithms (SVM) for iterations between CMFD and TH equations. The multipole representation method showed small differences of about 0.3% root mean square (RMS) error in converged assembly source distribution compared to a conventional MC simulation with ACE data at the same temperature. This is within two standard deviations of the real uncertainty. Eigenvalue differences were on the order of 10 pcm. Support vector machine regression was performed on-the-fly during MC simulations. Regression results of macroscopic cross sections parametrized by coolant density and fuel temperature were successful and eliminated the need of partial derivative tables generated from lattice codes. All of these new tools were integrated together to perform MC-CMFD-TH-SVM iterations. Results showed that inner iterations between CMFD-TH-SVM are needed to obtain a stable solution. 
655 7 |a Article 
773 |t Annals of Nuclear Energy