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Nuclear Technology Volume 158, 2007 - Issue 1: Best Estimate Methods—2004 Special Issue
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Technical Paper

Accurate Solution of the Nonlinear Partial Differential Equations from Thermal Hydraulics: Thermal Hydraulics

Vincent A. MousseauIdaho National Laboratory, P.O. Box 1625, MS 3840 Idaho Falls, Idaho 83415
Pages 26-35 | Published online: 10 Apr 2017

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Haihua Zhao, Lambert Fick, Alexander Heald, Quan Zhou, Samuel Richesson, Noah Sutton & Brandon Haugh. (2023) Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR). Nuclear Science and Engineering 197:5, pages 813-839.
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Haihua Zhao & Vincent A. Mousseau. (2013) Extended Forward Sensitivity Analysis for Uncertainty Quantification. Nuclear Technology 181:1, pages 184-195.
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