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Filtering by: Subject Gas cooled reactors -- Safety measures

Scaling analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors during a Depressurized Loss of Forced Convection Event

Creator:

Blake, Grant C.

Abstract:

The Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system capable of removing decay heat directly from the reactor core. Its modularity makes it scalable for use in reactors with various power levels. Work has previously been completed to support inclusion of the DRACS in liquid metal reactors...

Resource Type:

Masters Thesis
Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Creator:

Lenhof, Renae

Abstract:

A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal of the study was to better understand the safety and licensing implications of vented fuel technology. A Level 1 PRA was performed to determine the...

Resource Type:

Masters Thesis
Natural circulation scaling of a pressurized conduction cooldown event in the upper plenum of the modular high temperature gas reactor

Creator:

King, Brian M.

Abstract:

In a Modular High Temperature Gas Reactor (MHGTR), the Pressurized Conduction Cooldown (PCC) event is an accident scenario in which there is a loss of forced convection of the coolant through the system but the pressure boundary remains intact. When the PCC event occurs, natural circulation onsets which results in...

Resource Type:

Masters Thesis