THERMAL ANALYSIS OF SM-1 CORE III
Abstract
The thermal analysis performed on the SM-1 Core III for both steady state and transient conditions is reported. SM-1 Core III will be used as a test for Type 3 elements in a PM-2A Core. The steady state analysis indicated minimum departure from nucleate boiling ratios (DNBR) for both design and scram conditions above the minimum criteria of 1.5. Local nucleate boiling was noted in the hot internal channels and lattice passage at scram power conditions. Loss of flow transient results indicate DNBR's above 1.5, insuring that the core is safe from burnout. Bulk boiling was noted in the hot channels and lattice passage at scram power condition. (auth)
- Authors:
- Publication Date:
- Research Org.:
- Alco Products, Inc., Schenectady, NY (United States)
- OSTI Identifier:
- 4807322
- Report Number(s):
- APAE-105(Suppl.1)
- NSA Number:
- NSA-16-026583
- DOE Contract Number:
- AT(30-1)-2639
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
- Subject:
- REACTOR TECHNOLOGY; BOILING; BURNOUT; FLUID FLOW; LOSSES; NUCLEATE BOILING; OPERATION; POWER PLANTS; PRESSURE; REACTOR CORE; REACTOR SAFETY; REACTORS; SHUTDOWN; SM-1; TESTING; THERMODYNAMICS; TRANSIENTS; USES; WATER COOLANT; WATER MODERATOR
Citation Formats
Davidson, S. L. THERMAL ANALYSIS OF SM-1 CORE III. United States: N. p., 1962.
Web. doi:10.2172/4807322.
Davidson, S. L. THERMAL ANALYSIS OF SM-1 CORE III. United States. https://doi.org/10.2172/4807322
Davidson, S. L. 1962.
"THERMAL ANALYSIS OF SM-1 CORE III". United States. https://doi.org/10.2172/4807322. https://www.osti.gov/servlets/purl/4807322.
@article{osti_4807322,
title = {THERMAL ANALYSIS OF SM-1 CORE III},
author = {Davidson, S. L.},
abstractNote = {The thermal analysis performed on the SM-1 Core III for both steady state and transient conditions is reported. SM-1 Core III will be used as a test for Type 3 elements in a PM-2A Core. The steady state analysis indicated minimum departure from nucleate boiling ratios (DNBR) for both design and scram conditions above the minimum criteria of 1.5. Local nucleate boiling was noted in the hot internal channels and lattice passage at scram power conditions. Loss of flow transient results indicate DNBR's above 1.5, insuring that the core is safe from burnout. Bulk boiling was noted in the hot channels and lattice passage at scram power condition. (auth)},
doi = {10.2172/4807322},
url = {https://www.osti.gov/biblio/4807322},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jun 29 00:00:00 EDT 1962},
month = {Fri Jun 29 00:00:00 EDT 1962}
}
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