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Filtering by: Subject Gas cooled reactors -- Mathematical models

Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility

Creator:

Nelson, Benjamin L.

Abstract:

The Very High Temperature Reactor (VHTR) has two possible core configurations, a hexagonal prismatic and a pebble bed. It is essential that an experimental facility be built for the validation of computer codes for the safe operation of the VHTR. The scaling of the prismatic core configuration has been analyzed...

Resource Type:

Masters Thesis

Full Text:

-cooled Reactor Thermal Hydraulic Test Facility Abstract approved
Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

Creator:

Hallee, Brian Todd

Abstract:

The nuclear industry has long relied upon bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis accidents. These methods have been known to return highly-conservative results, limiting the operating conditions of the reactor. The Best-Estimate Plus Uncertainty (BEPU) method using a modernized version of the Code-Scaling,...

Resource Type:

Masters Thesis

Full Text:

bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis