Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf
Cover title
| Main Authors: | , |
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| Format: | Technical Report |
| Published: |
Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1977]
2014
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| Online Access: | http://hdl.handle.net/1721.1/89734 |
| _version_ | 1826209524678131712 |
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| author | Rodack, Thomas Wolf, Lothar |
| author2 | Massachusetts Institute of Technology. Department of Nuclear Engineering |
| author_facet | Massachusetts Institute of Technology. Department of Nuclear Engineering Rodack, Thomas Wolf, Lothar |
| author_sort | Rodack, Thomas |
| collection | MIT |
| description | Cover title |
| first_indexed | 2024-09-23T14:23:50Z |
| format | Technical Report |
| id | mit-1721.1/89734 |
| institution | Massachusetts Institute of Technology |
| last_indexed | 2024-09-23T14:23:50Z |
| publishDate | 2014 |
| publisher | Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1977] |
| record_format | dspace |
| spelling | mit-1721.1/897342019-04-12T14:14:16Z Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf Rodack, Thomas Wolf, Lothar Massachusetts Institute of Technology. Department of Nuclear Engineering TK9008.M41 N96 no.206 Nuclear fuel elements -- Computer programs Nuclear fuel elements -- Thermal properties Nuclear reactors -- Fluid dynamics Cover title "August 1977." Also issued as a Nucl. E. and M.S. thesis by the first author and supervised by the second author, MIT Depts. of Nuclear and Mechanical Engineering, 1977 Includes bibliographical references (pages 242-246) The thermal-hydraulic (T-H) models and solution schemes employed by the MEKIN computer code have been examined. The effects of T-H input parameters on- predicted fuel temperatures and coolant densities were determined in transient analyses. Consideration was limited primarily to a simulated PWR control rod ejection transient. Limitations to the use of MEKIN that arise because of simplifying assumptions in the T-H models are discussed. Computation time may be reduced without altering the results of a transient analysis if appropriate MEKIN options are selected. Guidelines are presented to facilitate the selection of these options. Suggestions for improvement of the code are also ma:de. 2014-09-16T23:36:51Z 2014-09-16T23:36:51Z 1977 Technical Report http://hdl.handle.net/1721.1/89734 857286221 MITNE ; no. 206 283 pages application/pdf Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1977] |
| spellingShingle | TK9008.M41 N96 no.206 Nuclear fuel elements -- Computer programs Nuclear fuel elements -- Thermal properties Nuclear reactors -- Fluid dynamics Rodack, Thomas Wolf, Lothar Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf |
| title | Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf |
| title_full | Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf |
| title_fullStr | Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf |
| title_full_unstemmed | Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf |
| title_short | Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf |
| title_sort | sensitivity study of the assembly averaged thermal hydraulic models of the mekin computer code in power transients by thomas rodack and lothar wolf |
| topic | TK9008.M41 N96 no.206 Nuclear fuel elements -- Computer programs Nuclear fuel elements -- Thermal properties Nuclear reactors -- Fluid dynamics |
| url | http://hdl.handle.net/1721.1/89734 |
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