Safety Analysis of CiADS Sub-Critical Reactor Fuel Cladding under Beam Transients

被引：0
|
作者：
Zhang Q. [1 ,2 ]
Gu L. [1 ,2 ]
Peng T. [1 ]
Sheng X. [1 ]
机构：
[1] Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou
[2] University of Chinese Academy of Sciences, Beijing
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2018年 / 39卷 / 05期
关键词：
Beam trip; CiADS; Fatigue life; Stress analysis;
D O I：
10.13832/j.jnpe.2018.05.0051
中图分类号：
学科分类号：
摘要：
The response characteristics of the fuel rods in the sub-critical reactor of China Initiative Accelerator Driven System (CiADS) under beam trip were simulated by the reactor system analysis program RELAP5 mod4.0. The fatigue life of the fuel cladding in CiADS under beam trip is calculated by ANSYS 17.0. The fatigue life of the fuel cladding in hundred megawatt Accelerator Driven Sub-critical System (ADS) to be designed in China is predicted. The results show that the power of CiADS subcritical reactor instantaneously falls to 2.156% of full power when beam trip lost. The fatigue life of the fuel cladding of the CiADS subcritical reactor under beam trip is above 108. the beam trip will not cause fatigue damage to fuel cladding in hundred megawatt ADS to be designed in China. © 2018, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
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页码：051 / 057
页数：6
相关论文
共 14 条
  • [1] Abderrahim H.A., Galambos J., Gohar Y., Et al., Accelerator and target technology for accelerator driven transmutation and energy production[M/OL], (2010)
  • [2] Liu P., Chen X.N., Rineiski A., Et al., Transient analysis of the 400MWth-class EFIT accelerator driven transmuter with the multi-physics code: SIMMER-III, Nuclear Engineering and Design, 240, 10, pp. 3481-3494, (2010)
  • [3] Sugawara T., Nishihara K., Tsujimoto K., Transient analysis for lead-bismuth cooled accelerator-driven system, Annals of Nuclear Energy, 55, pp. 238-247, (2013)
  • [4] Ahmad A., Lindley B.A., Parks G.T., Accelerator-induced transients in Accelerator Driven Subcritical Reactors, Nuclear Inst & Methods in Physics Research A, 696, 6, pp. 55-65, (2012)
  • [5] Xue S., Jin M., Wang G., Et al., Fuel cladding integrity analysis during beam trip transients for China lead-based demonstration reactor, Annals of Nuclear Energy, 83, pp. 94-100, (2015)
  • [6] Forster R.A., Godfrey T.N.K., MCNP - a general Monte Carlo code for neutron and photon transport, Monte-Carlo Methods and Applications in Neutronics, Photonics and Statistical Physics, pp. 33-55, (1985)
  • [7] Cheng S.-K., Todreas N., Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles-Bundle friction factors, Nuclear Engineering and Design, 92, pp. 227-251, (1986)
  • [8] Borishanskii V.M., Gotovskii M.A., Firsova E.V., Heat transfer to liquid metals in longitudinally wetted bundles of rods, Soviet Atomic Energy, 27, 6, pp. 1347-1350, (1969)
  • [9] RCC-MR 111-2007. Subsection Z: appendicies A3 and A9, (2007)
  • [10] Pacio J., Wetzel T., Doolaard H., Et al., Thermal-hydraulic study of the LBE-cooled fuel assembly in the MYRRHA reactor: Experiments and simulations, Nuclear Engineering & Design, 312, pp. 327-337, (2017)
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