TY - JOUR
T1 - Fuel temperature analysis method for channel-blockage accident in HTTR
AU - Maruyama, So
AU - Fujimoto, Nozomu
AU - Sudo, Yukio
AU - Kiso, Yoshihiro
AU - Hayakawa, Hitoshi
N1 - Funding Information:
The HTTR is a helium-cooled, graphite-moderated high-temperature reactor with 30 MW thermal power and a reactor outlet coolant temperature of 950°C. This maximum outlet coolant temperature of 950°C is achieved in the high-temperature test operation mode. The HTTR core consists of 30 fuel columns, 16 control rod guide columns and 15 replaceable reflector columns. It is surrounded by permanent reflector blocks and side shields as shown in Fig. 1. The total weight of the core is supported by the support skirt of the reactor pressure vessel through the hot plenum blocks, support posts and core bottom graphite structures and steel structures.
Copyright:
Copyright 2015 Elsevier B.V., All rights reserved.
PY - 1994/9/2
Y1 - 1994/9/2
N2 - During operation of the High Temperature Engineering Test Reactor (HTTR), coolability must be maintained without core damage under all postulated accident conditions. Channel blockage of a fuel element was selected as one of the design-basis accidents in the safely evaluation of the reactor. The maximum fuel temperature for such a scenario has been evaluated in the safety analysis and is compared to the core damage limits. For the design of the HTTR, an in-core thermal and hydraulic analysis code Flownet/trump was developed. This code calculates fuel temperature distrubution, not only for a channel blockage accident but also for transient conditions. The validation of flownet/trump code was made by comparison of the analytical results with the results of thermal and hydraulic tests by the Helium Engineering Demonstration Loop (HENDEL) multi-channel test rig (T1-M), which simulated one fuel column in the core. The analytical results agreed well with experiments in which the HTTR operating conditions were simulated. The maximum fuel temperature during a channel blockage accident is 1653°C. Therefore, it is confirmed that the integrity of the core is maintained during a channel blockage accident.
AB - During operation of the High Temperature Engineering Test Reactor (HTTR), coolability must be maintained without core damage under all postulated accident conditions. Channel blockage of a fuel element was selected as one of the design-basis accidents in the safely evaluation of the reactor. The maximum fuel temperature for such a scenario has been evaluated in the safety analysis and is compared to the core damage limits. For the design of the HTTR, an in-core thermal and hydraulic analysis code Flownet/trump was developed. This code calculates fuel temperature distrubution, not only for a channel blockage accident but also for transient conditions. The validation of flownet/trump code was made by comparison of the analytical results with the results of thermal and hydraulic tests by the Helium Engineering Demonstration Loop (HENDEL) multi-channel test rig (T1-M), which simulated one fuel column in the core. The analytical results agreed well with experiments in which the HTTR operating conditions were simulated. The maximum fuel temperature during a channel blockage accident is 1653°C. Therefore, it is confirmed that the integrity of the core is maintained during a channel blockage accident.
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U2 - 10.1016/0029-5493(94)90052-3
DO - 10.1016/0029-5493(94)90052-3
M3 - Article
AN - SCOPUS:0028761474
VL - 150
SP - 69
EP - 80
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
SN - 0029-5493
IS - 1
ER -