Tally derivative based surrogate models for faster Monte Carlo multiphysics

Existing neutron transport methods used in the nuclear power industry rely on a complex toolchain of modeling and simulation software. Each link in this chain applies various approximations to the spatial, angular, and energy distributions of the problem variables; and these approximations can limit solver predictive capabilities. Monte Carlo (MC) neutron transport is a high-fidelity method that can relax many of these approximations and possibly replace much of the existing toolchain. However, MC neutron transport is also very slow, particularly when coupled into a multiphysics solver. Some researchers have published runtime costs of over 100 000 cpuhours to converge a quarter-core multiphysics problem with MC --

Name thesis:degree_name

Doctoral

Department dc:contributor.department

Massachusetts Institute of Technology. Department of Nuclear Science and Engineering

Grantor dc:publisher

Massachusetts Institute of Technology

Year dc:date.issued

2020

Author dc:creator

• Harper, Sterling(Sterling M.)

Advisor dc:contributor.advisor

• Benoit Forget and Kord Smith.

• Nuclear Science and Engineering.

Statement dc:rights

• MIT theses may be protected by copyright. Please reuse MIT thesis content according to the MIT Libraries Permissions Policy, which is available through the URL provided.

Licence dc:rights.uri

• http://dspace.mit.edu/handle/1721.1/7582

Language dc:language.iso

eng

Handle dc:identifier.uri

https://hdl.handle.net/1721.1/129109

OAI identifier oai:identifier

oai:dspace.mit.edu:1721.1/129109