ORECA-1: a digital computer code for simulating the dynamics of HTGR cores for emergency cooling analyses
Description
ORECA-I predicts the three-dimensional transient thermal-hydraulic behavior of the core of a high-temperature gas-cooled reactor (HTGR) for specified emergency shutdown conditions. It was modeled after the RECA code (Reactor Emergency Cooling Analysis) by the General Atomic Company to provide a better understanding of the relative importance of mechanisms for afterheat removal and enable independent evaluation of the General Atomic Company analyses. Descriptions are given of the modeling and solution techniques, and examples of transient calculations are presented. Predictions of several types of accident transients were in good agreement with the results of RECA calculations. The relatively small computation times required for ORECA also make it convenient to use for model and parameter sensitivity studies
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS.Files
7268665.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 57 p.
- Report number
- ORNL-TM--5159
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7268665
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; ECCS; FLUID FLOW; HEAT TRANSFER; HTGR TYPE REACTORS; O CODES; PERFORMANCE; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; SIMULATION; VRAIN REACTOR
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY
Optional Information
- Notes
- Available from NTIS. $4.50.