Fuel management of the HTR-10 including the equilibrium state and the running-in phase
Yang Yongwei; Luo Zhengpei; Jing Xingqing; Wu Zongxin, E-mail: maoc@te.tsinghua.edu.cn2002
AbstractAbstract
[en] The mode of fuel management of the HTR-10 was studied, including the simulation of the fuel shuffling process and the measurement of the burnup of a fuel element. The prior consideration was the design of the equilibrium state. Based on this the fuel loading of the initial core and the fuel shuffling mode from the initial core through the running-in phase into the equilibrium state were studied. The code system VSOP was used for the physical layout of the HTR-10 at the equilibrium state and in the running-in phase. For the equilibrium state, in order to lessen the difference between the peak and the average burnup, 5-fuel-passage-through-the-core was chosen for the fuel management. The average burnup of the spent fuel for the equilibrium core is 80000 MWd t-1, and the peak value of it is less than 100000 MWd t-1 when the burnup of the recycled fuel element is under 72000 MWd t-1. The mixture of fuel element and graphite element was used for the initial core loading, the volume fractions of the fuel and the graphite elements were 0.57 and 0.43, respectively. During the running-in phase, the volume fraction of graphite will decrease with the fresh fuel elements being loaded from the top of the core and the graphite elements discharged from the bottom of the core. The fuel shuffling mode is similar to that of the equilibrium state. The burnup limit of recycled fuel element is also 72000 MWd t-1 and the peak burnup is less than 100000 MWd t-1. Finally the core will be full of fuel elements with a certain profile of burnup and reaches the equilibrium state. According to the characteristics of the pebble-bed high temperature gas-cooled reactor, a calibrating method of concentration of 137Cs was proposed for the measurement of fuel burnup
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S0029549302001838; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HOMOGENEOUS REACTORS, HTGR TYPE REACTORS, MANAGEMENT, NUCLEAR MATERIALS MANAGEMENT, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, TEST FACILITIES, TEST REACTORS
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