INGRES: a computer code for the rate of air ingress into an HTGR following a design-basis depressurization accident
Description
The computer program INGRES was written to calculate the rate of air ingress into the prestressed concrete reactor vessel after a design-basis depressurization accident in a high-temperature gas-cooled reactor. The model includes the free convection loop that can occur in a cold-leg break, the expansion and contraction air exchange mechanisms, and the conversion of oxygen to carbon monoxide. Results are presented for the 2000-MW(t) Summit Power Station and the 3000-MW(t) Fulton Generating Station and are compared to computational results provided by the General Atomic Company. The results agree reasonably well even though some differences exist in the two models
Availability note (English)
MF available from INIS under the Report Number.
Files
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Additional details
Publishing Information
- Imprint Pagination
- 32 p.
- Report number
- ORNL-TM--5144
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7240425
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AIR; COMPUTER CODES; CONTAINMENT; DEPRESSURIZATION; FULTON-1 REACTOR; HTGR TYPE REACTORS; I CODES; PRESSURE VESSELS; SUMMIT-1 REACTOR
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS