Browse Dept. of Nuclear, Plasma, and Radiological Engineering by Subject "Uncertainty quantification"
Now showing items 1-2 of 2
(2015-12-03)Forward quantification of uncertainties in code responses require knowledge of input model parameter uncertainties. Nuclear thermal-hydraulics codes such as RELAP5 and TRACE do not provide any information on physical model ...
(2015-12-10)Best-estimate codes have been developed in the nuclear industry to design and license nuclear power plants to a greater degree of accuracy and safety assurance. Such codes necessitate efforts to qualify their validity, ...