Published May 1980
| Version v1
Report
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Development of models for the sodium version of the two-phase three-dimensional thermal hydraulics code THERMIT
Description
Several different models and correlations were developed and incorporated in the sodium version of THERMIT, a thermal-hydraulics code written at MIT for the purpose of analyzing transients under LMFBR conditions. This includes: a mechanism for the inclusion of radial heat conduction in the sodium coolant as well as radial heat loss to the structure surrounding the test section. The fuel rod conduction scheme was modified to allow for more flexibility in modelling the gas plenum regions and fuel restructuring. The formulas for mass and momentum exchange between the liquid and vapor phases were improved. The single phase and two phase friction factors were replaced by correlations more appropriate to LMFBR assembly geometry
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A09/MF A01.Files
12616065.pdf
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Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 179 p.
- Report number
- DOE/ET/37218--3
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12616065
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR SAFETY; SODIUM; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; TWO-PHASE FLOW
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; LIQUID METAL COOLED REACTORS; METALS; REACTORS; SAFETY
Optional Information
- Secondary number(s)
- MIT-EL--80-010.