Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents

Mochizuki, H. ; Koike, M.H. ; Sakai, T.

Amsterdam : Elsevier
ISSN:
0029-5493
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
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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