Reactor agnostic multi-group cross section generation for fine-mesh deterministic neutron transport simulations

Reactor agnostic multi-group cross section generation for fine-mesh deterministic neutron transport simulations

Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2017.

Bibliographic Details
Main Author: Boyd, William Robert Dawson, III
Other Authors: Kord Smith and Benoit Forget.
Format: Thesis
Language:eng
Published: Massachusetts Institute of Technology 2017
Subjects:
Nuclear Science and Engineering.
Online Access:http://hdl.handle.net/1721.1/112525

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