Published July 1979
| Version v1
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Computer simulation of natural circulation in FFTF secondary loops
Description
A thermal/hydraulic model of the FFTF secondary heat transport loop has been calibrated against transient natural circulation test data collected March to May 1979. The tests verified that the transition to natural convective flow could be effected from near isothermal conditions without excessive cooling at the air dump heat exchangers. Key empirical parameters of pressure drop and heat loss were found to be at 88% and 81% of pretest estimates, respectively. Pretest piping thermal transport and flow calculational models required no further revision to produce good agreement with test data
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
11541270.pdf
Files
(5.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- HEDL-SA--1920S
Conference
- Title
- Specialists meeting on decay heat removal and natural circulation in FBR's.
- Dates
- 28 - 29 Feb 1980.
- Place
- Upton, NY, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11541270
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; FFTF REACTOR; HEAT EXCHANGERS; HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; NATURAL CONVECTION; PRESSURE DROP; REACTOR SAFETY; SECONDARY COOLANT CIRCUITS
- Descriptors DEC
- ACCIDENTS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; TEST REACTORS
Optional Information
- Secondary number(s)
- CONF-800226--2.