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contributor authorHonda, Yuki
contributor authorFujimoto, Nozomu
contributor authorSawahata, Hiroaki
contributor authorTakada, Shoji
contributor authorSawa, Kazuhiro
date accessioned2017-11-25T07:18:46Z
date available2017-11-25T07:18:46Z
date copyright2016/20/12
date issued2017
identifier issn2332-8983
identifier otherners_3_1_011005.pdf
identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235401
description abstractThe high-temperature engineering test reactor (HTTR) is a block-type high-temperature gas-cooled reactor (HTGR). There are 32 control rods (16 pairs) in the HTTR. Six of the pairs of control rods are located in a core region and the remainder are located in a reflector region surrounding the core. Inserting all control rods simultaneously at the reactor scram in a full-power operation presents difficulty in maintaining the integrity of the metallic sleeve of the control rod because the core temperature of the HTTR is too high. Therefore, a two-step control rod insertion method is adopted for the reactor scram. The calculated control rod worth at the first step showed a larger underestimation than the measured value in the second step, although the calculated results of the excess reactivity tests showed good agreement with the measured result in the criticality tests of the HTTR. It is concluded that a cell model for the control rod guide block with the control rod in the reflector region is not suitable. In addition, in the core calculation, the macroscopic cross section of a homogenized region of the control rod guide block with the control rod is used. Therefore, it would be one of the reasons that the neutron flux distribution around the control rod in control rod guide block in the reflector region cannot be simulated accurately by the conventional cell model. In the conventional cell model, the control rod guide block is surrounded by the fuel blocks only, although the control rods in the reflector region are surrounded by both the fuel blocks and the reflector blocks. The difference of the neutron flux distribution causes the large difference of a homogenized macroscopic cross-section set of the control rod guide block with the control rod. Therefore, in this paper, the cell model is revised for the control rod guide block with the control rod in the reflector region to account for the actual configuration around the control rod guide block in the reflector region. The calculated control rod worth at the first step using the improved cell model shows better results than the previous one.
publisherThe American Society of Mechanical Engineers (ASME)
titleStudy on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor
typeJournal Paper
journal volume3
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4033813
journal fristpage11005
journal lastpage011005-6
treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001
contenttypeFulltext


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