Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents
| ISSN: |
0029-5493
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|---|---|
| Source: |
Elsevier Journal Backfiles on ScienceDirect 1907 - 2002
|
| Topics: |
Energy, Environment Protection, Nuclear Power Engineering
|
| Type of Medium: |
Electronic Resource
|
| URL: |
| _version_ | 1798291141321293824 |
|---|---|
| autor | Mochizuki, H. Koike, M.H. Sakai, T. |
| autorsonst | Mochizuki, H. Koike, M.H. Sakai, T. |
| book_url | http://dx.doi.org/10.1016/0029-5493(93)90145-Y |
| datenlieferant | nat_lic_papers |
| fussnote | In the case of a loss-of-coolant accident (LOCA) with coincident loss of emergency coolant injection (LOECI), core cooling is generally very severe. However, as the ATR plant has heavy water at about 60^oC in the core, decay heat can be removed by the heavy water cooling system. Separate-effects tests relating to heavy water cooling were conducted with each setup. The important thermal hydraulics was radiation heat transfer, ballooning of a pressure tube, contact conductance between the pressure tube and a calandria tube and critical heat flux of the calandria tube. Constants and correlations obtained by the tests were incorporated into several codes to assess the core cooling. Long term core cooling capability with the heavy water cooling system was assessed. The core was cooled without melting under the postulated events due to inherent characteristics of the ATR. |
| hauptsatz | hsatz_simple |
| identnr | NLZ185545424 |
| issn | 0029-5493 |
| journal_name | Nuclear Engineering and Design |
| materialart | 1 |
| package_name | Elsevier |
| publikationsort | Amsterdam |
| publisher | Elsevier |
| reference | 144 (1993), S. 293-303 |
| search_space | articles |
| shingle_author_1 | Mochizuki, H. Koike, M.H. Sakai, T. |
| shingle_author_2 | Mochizuki, H. Koike, M.H. Sakai, T. |
| shingle_author_3 | Mochizuki, H. Koike, M.H. Sakai, T. |
| shingle_author_4 | Mochizuki, H. Koike, M.H. Sakai, T. |
| shingle_catch_all_1 | Mochizuki, H. Koike, M.H. Sakai, T. Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents 0029-5493 00295493 Elsevier |
| shingle_catch_all_2 | Mochizuki, H. Koike, M.H. Sakai, T. Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents 0029-5493 00295493 Elsevier |
| shingle_catch_all_3 | Mochizuki, H. Koike, M.H. Sakai, T. Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents 0029-5493 00295493 Elsevier |
| shingle_catch_all_4 | Mochizuki, H. Koike, M.H. Sakai, T. Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents 0029-5493 00295493 Elsevier |
| shingle_title_1 | Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents |
| shingle_title_2 | Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents |
| shingle_title_3 | Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents |
| shingle_title_4 | Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents |
| sigel_instance_filter | dkfz geomar wilbert ipn albert fhp |
| source_archive | Elsevier Journal Backfiles on ScienceDirect 1907 - 2002 |
| timestamp | 2024-05-06T08:27:54.688Z |
| titel | Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents |
| titel_suche | Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents In the case of a loss-of-coolant accident (LOCA) with coincident loss of emergency coolant injection (LOECI), core cooling is generally very severe. However, as the ATR plant has heavy water at about 60^oC in the core, decay heat can be removed by the heavy water cooling system. Separate-effects tests relating to heavy water cooling were conducted with each setup. The important thermal hydraulics was radiation heat transfer, ballooning of a pressure tube, contact conductance between the pressure tube and a calandria tube and critical heat flux of the calandria tube. Constants and correlations obtained by the tests were incorporated into several codes to assess the core cooling. Long term core cooling capability with the heavy water cooling system was assessed. The core was cooled without melting under the postulated events due to inherent characteristics of the ATR. |
| topic | ZP |
| uid | nat_lic_papers_NLZ185545424 |