Recommendations for modeling upper plenum injection system for a pressurized water reactor
The present work examines the unique heat transfer modeling problems associated with analysis of performance of an upper plenum emergency core cooling injection system during a postulated Loss-of-Coolant Accident (LOCA) in a pressurized water reactor. The particular system under study consis...
| Main Authors: | , |
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| Format: | Technical Report |
| Language: | en_US |
| Published: |
MIT Energy Laboratory
2006
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| Subjects: | |
| Online Access: | http://hdl.handle.net/1721.1/31333 |
| _version_ | 1811086272814383104 |
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| author | Griffith, Peter Kan, John |
| author_facet | Griffith, Peter Kan, John |
| author_sort | Griffith, Peter |
| collection | MIT |
| description | The present work examines the unique heat transfer modeling
problems associated with analysis of performance of an upper plenum
emergency core cooling injection system during a postulated
Loss-of-Coolant Accident (LOCA) in a pressurized water reactor.
The particular system under study consists of four 4-inch pipes
conveying emergency core cooling water from outside the pressure vessel
through four spare control and rod mechanism housings and internal
pipings, discharging the water directly over the top of the reactor
core.
Previously, it has been assumed that the water injected into the
upper plenum passes through the reactor core to the lower plenum
without any heat interaction with the fuel rods during a LOCA. This
simplified model neglects the many beneficial and adverse effects that
accompany the upper plenum injection.
This study is undertaken to examine the following items
· heat transfer to the emergency core coolant before reaching
the core
· flow and heat transfer through the reactor core
· reflood heat transfer.
The phenomena occurring will be delineated and recommendations
made for calculating both conservative and best estimate values. The
method of solving these problems will be illustrated in a series of
examples given in the appendices. |
| first_indexed | 2024-09-23T13:23:36Z |
| format | Technical Report |
| id | mit-1721.1/31333 |
| institution | Massachusetts Institute of Technology |
| language | en_US |
| last_indexed | 2024-09-23T13:23:36Z |
| publishDate | 2006 |
| publisher | MIT Energy Laboratory |
| record_format | dspace |
| spelling | mit-1721.1/313332019-04-12T08:25:46Z Recommendations for modeling upper plenum injection system for a pressurized water reactor Griffith, Peter Kan, John Nuclear fuel elements. Pressurized water reactors |x Cooling. Pressurized water reactors |x Safety measures. The present work examines the unique heat transfer modeling problems associated with analysis of performance of an upper plenum emergency core cooling injection system during a postulated Loss-of-Coolant Accident (LOCA) in a pressurized water reactor. The particular system under study consists of four 4-inch pipes conveying emergency core cooling water from outside the pressure vessel through four spare control and rod mechanism housings and internal pipings, discharging the water directly over the top of the reactor core. Previously, it has been assumed that the water injected into the upper plenum passes through the reactor core to the lower plenum without any heat interaction with the fuel rods during a LOCA. This simplified model neglects the many beneficial and adverse effects that accompany the upper plenum injection. This study is undertaken to examine the following items · heat transfer to the emergency core coolant before reaching the core · flow and heat transfer through the reactor core · reflood heat transfer. The phenomena occurring will be delineated and recommendations made for calculating both conservative and best estimate values. The method of solving these problems will be illustrated in a series of examples given in the appendices. Final report for research project sponsored by Northeast Utilities Service Co. 2006-03-13T16:00:59Z 2006-03-13T16:00:59Z 1978-10 Technical Report 04842804 http://hdl.handle.net/1721.1/31333 en_US MIT-EL 78-031 1978910 bytes application/pdf application/pdf MIT Energy Laboratory |
| spellingShingle | Nuclear fuel elements. Pressurized water reactors |x Cooling. Pressurized water reactors |x Safety measures. Griffith, Peter Kan, John Recommendations for modeling upper plenum injection system for a pressurized water reactor |
| title | Recommendations for modeling upper plenum injection system for a pressurized water reactor |
| title_full | Recommendations for modeling upper plenum injection system for a pressurized water reactor |
| title_fullStr | Recommendations for modeling upper plenum injection system for a pressurized water reactor |
| title_full_unstemmed | Recommendations for modeling upper plenum injection system for a pressurized water reactor |
| title_short | Recommendations for modeling upper plenum injection system for a pressurized water reactor |
| title_sort | recommendations for modeling upper plenum injection system for a pressurized water reactor |
| topic | Nuclear fuel elements. Pressurized water reactors |x Cooling. Pressurized water reactors |x Safety measures. |
| url | http://hdl.handle.net/1721.1/31333 |
| work_keys_str_mv | AT griffithpeter recommendationsformodelingupperplenuminjectionsystemforapressurizedwaterreactor AT kanjohn recommendationsformodelingupperplenuminjectionsystemforapressurizedwaterreactor |