Modeling of fuel-to-steel heat transfer in core disruptive accidents
"June 1980."
| Main Authors: | , , |
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| Other Authors: | |
| Format: | Technical Report |
| Published: |
Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1980]
2014
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| Subjects: | |
| Online Access: | http://hdl.handle.net/1721.1/89739 |
| _version_ | 1811097290652254208 |
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| author | Smith, Russell Charles Rohsenow, Warren M. Kazimi, Mujid S. |
| author2 | Massachusetts Institute of Technology. Department of Nuclear Engineering |
| author_facet | Massachusetts Institute of Technology. Department of Nuclear Engineering Smith, Russell Charles Rohsenow, Warren M. Kazimi, Mujid S. |
| author_sort | Smith, Russell Charles |
| collection | MIT |
| description | "June 1980." |
| first_indexed | 2024-09-23T16:57:19Z |
| format | Technical Report |
| id | mit-1721.1/89739 |
| institution | Massachusetts Institute of Technology |
| last_indexed | 2024-09-23T16:57:19Z |
| publishDate | 2014 |
| publisher | Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1980] |
| record_format | dspace |
| spelling | mit-1721.1/897392019-04-11T04:11:15Z Modeling of fuel-to-steel heat transfer in core disruptive accidents Smith, Russell Charles Rohsenow, Warren M. Kazimi, Mujid S. Massachusetts Institute of Technology. Department of Nuclear Engineering U.S. Nuclear Regulatory Commission TK9008.M41 N96 no.233 Liquid metal fast breeder reactors -- Safety measures Heat -- Transmission -- Mathematical models Nuclear fuel elements "June 1980." Also issued as a Ph. D. thesis by the first author, MIT Dept. of Nuclear Engineering, 1980 Includes bibliographical references (pages 110-111) A mathematical model for direct-contact boiling heat transfer between immiscible fluids was developed and tested experimentally. The model describes heat transfer from a hot fluid bath to an ensemble of droplets of a cooler fluid that boils as it passes through the hot fluid. The mathematical model is based on single bubble correlations for the heat transfer and a drift-flux model for the fluid dynamics. The model yields a volumetric heat transfer coefficient as a function of the initial diameter, velocity and volume fraction of the dispersed component. An experiment was constructed to boil cyclopentane droplets in water. The mathematical and experimental results agreed reasonably well. The results were applied to investigate the possibility of steel vaporization during a hypothetical core disruptive accident in a liquid metal fast breeder reactor. The model predicts that substantial steel vaporization may occur in core disruptive accidents, if the steel reaches its saturation temperature rapidly enough. The potential importance of steel vaporization is dependent on the accident scenario. Report issued under contract with the U.S. Nuclear Regulatory Commission NRC-04-77-126 2014-09-16T23:37:23Z 2014-09-16T23:37:23Z 1980 Technical Report http://hdl.handle.net/1721.1/89739 857463357 MITNE ; no. 233 111 pages application/pdf Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1980] |
| spellingShingle | TK9008.M41 N96 no.233 Liquid metal fast breeder reactors -- Safety measures Heat -- Transmission -- Mathematical models Nuclear fuel elements Smith, Russell Charles Rohsenow, Warren M. Kazimi, Mujid S. Modeling of fuel-to-steel heat transfer in core disruptive accidents |
| title | Modeling of fuel-to-steel heat transfer in core disruptive accidents |
| title_full | Modeling of fuel-to-steel heat transfer in core disruptive accidents |
| title_fullStr | Modeling of fuel-to-steel heat transfer in core disruptive accidents |
| title_full_unstemmed | Modeling of fuel-to-steel heat transfer in core disruptive accidents |
| title_short | Modeling of fuel-to-steel heat transfer in core disruptive accidents |
| title_sort | modeling of fuel to steel heat transfer in core disruptive accidents |
| topic | TK9008.M41 N96 no.233 Liquid metal fast breeder reactors -- Safety measures Heat -- Transmission -- Mathematical models Nuclear fuel elements |
| url | http://hdl.handle.net/1721.1/89739 |
| work_keys_str_mv | AT smithrussellcharles modelingoffueltosteelheattransferincoredisruptiveaccidents AT rohsenowwarrenm modelingoffueltosteelheattransferincoredisruptiveaccidents AT kazimimujids modelingoffueltosteelheattransferincoredisruptiveaccidents |