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contributor authorOno, Masato
contributor authorShimizu, Atsushi
contributor authorKondo, Makoto
contributor authorShimazaki, Yosuke
contributor authorShinohara, Masanori
contributor authorTochio, Daisuke
contributor authorIigaki, Kazuhiko
contributor authorNakagawa, Shigeaki
contributor authorTakada, Shoji
contributor authorSawa, Kazuhiro
date accessioned2017-11-25T07:18:45Z
date available2017-11-25T07:18:45Z
date copyright2016/10/12
date issued2016
identifier issn2332-8983
identifier otherners_2_4_044502.pdf
identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235387
description abstractIn the loss of core cooling test using High Temperature engineering Test Reactor (HTTR), the forced cooling of the reactor core is stopped without inserting control rods into the core and, furthermore, without cooling by the vessel cooling system (VCS) to verify safety evaluation codes to investigate the inherent safety of high-temperature gas-cooled reactor (HTGR) be secured by natural phenomena to make it possible to design a severe accident-free reactor. The VCS passively removes the retained residual heat and the decay heat from the core via the reactor pressure vessel (RPV) by natural convection and thermal radiation. In the test, the local temperature was supposed to exceed the limit from the viewpoint of long-term use at the uncovered water-cooling tube without thermal reflectors in the VCS, although the safety of reactor is kept. Through a cold test, which was carried out by non-nuclear heat input from helium gas circulators (HGCs) by stopping water flow in the VCS, the local higher temperature position was specified in the uncovered water-cooling tube of the VCS, although the temperature was sufficiently lower than the maximum allowable working temperature, and the natural circulation of water had an insufficient cooling effect on the temperature of the water-cooling tube below 1°C. Then, a new safe and secured procedure for the loss of core cooling test was established, which will be carried out soon after the restart of HTTR.
publisherThe American Society of Mechanical Engineers (ASME)
titleInvestigation of Countermeasure Against Local Temperature Rise in Vessel Cooling System in Loss of Core Cooling Test Without Nuclear Heating
typeJournal Paper
journal volume2
journal issue4
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4032478
journal fristpage44502
journal lastpage044502-4
treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 004
contenttypeFulltext


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