An Analysis of Heat Transfer after Loss of Primary Coolant in the SP-100 Reactor System
Abstract
This study determines design guidelines for the SP-100 space reactor core cooling system after a loss of coolant accident. The Thermal Systems Analysis Code (TSAP) calculated the temperatures within the fuel assemblies as a result of the fuel decay heat. TSAP is a lumped-parameter network analysis code capable of performing radiative and conductive heat transfer analysis. The reactor core was assumed to void of coolant instantaneously following a LOCA. The reactor core model consisted of individual fuel pin assemblies containing 36 fuel pins surrounding a central cooling channel. This central cooling channel, or bayonet, is a secondary cooling loop within the reactor core. The bayonet cooling is a safety feature designed to keep the core from reaching temperatures at which the uranium dissociates from the uranium-nitride fuel. TSAP calculated the fuel pin temperatures due to decay heat transient. The performance of the bayonets within a generic reactor core was compared to an actual design. Design guidance was established based on the performance of the bayonets in the generic core.
Document Details
- Document Type
- Technical Report
- Publication Date
- Mar 01, 1988
- Accession Number
- ADA194619
Entities
People
- Donald W. Robbins
Organizations
- Air Force Institute of Technology