Analysis of the axial fitting clearance between the fuel rod and the end seat in CIADS

Ya-Feng Shu; Yong-Wei Yang; Xin Sheng; Kang Chen; De-Liang Fan; Lu Zhang

doi:10.1007/s41365-016-0143-1

Your Location：

Home >

Browse articles >

Analysis of the axial fitting clearance between the fuel rod and the end seat in CIADS

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2021-02-23

- Analysis of the axial fitting clearance between the fuel rod and the end seat in CIADS
- Nuclear Science and Techniques Vol. 27, Issue 6, Article number: 139(2016)
- Affiliations：
  
  1.Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
- Author bio：
  
  Corresponding author. E-mail address: yangyongwei@impcas.ac.cn
- Funds：
- DOI：10.1007/s41365-016-0143-1
  CLC：
Scan for full text
Ya-Feng Shu, Yong-Wei Yang, Xin Sheng, et al. Analysis of the axial fitting clearance between the fuel rod and the end seat in CIADS. [J]. Nuclear Science and Techniques 27(6):139(2016)
DOI：

Ya-Feng Shu, Yong-Wei Yang, Xin Sheng, et al. Analysis of the axial fitting clearance between the fuel rod and the end seat in CIADS. [J]. Nuclear Science and Techniques 27(6):139(2016) DOI： 10.1007/s41365-016-0143-1.

摘要

Abstract

The fuel assembly is key structure in China Initiative Accelerator Driven System (CIADS), and the axial fitting clearance (AFC) for the fuel assembly design is an essential subject of study. In this paper, different methods are used to calculate critical stress in cylindrical shells. Because the thermal expansion of fuel assembly outer tube is larger than that of the cladding of fuel rod, enough space should be reserved between the upper end plug and upper seat slot. The collapse critical compressive stress of the cladding is obtained numerically through ANSYS simulation calculation. The AFC range between the fuel rod cladding and the end seat due to the displacement of thermal expansion is given by the theoretical formulas and ANSYS buckling analysis. These provide a reference for the AFC design of the reactor fuel assembly.

关键词

Keywords

Thermal expansionCritical stressAFC calculationANSYS simulation

references

W.L. Zhan, H.S. Xu, Advanced Fission Energy Program - ADS Transmutation System. Bulletin of Chinese Academy of Sciences. 27, 375-383(2012). doi: 10.3969/j.issn.1000-3045.2012.03.017http://doi.org/10.3969/j.issn.1000-3045.2012.03.017

M.S. Ismail, J. Purbolaksono, A. Andriyana et al., The use of initial imperfection approach in design process and buckling failure evaluation of axially compressed composite cylindrical shells. Eng. Fail. Anal. 51, 20-28(2015). doi: 10.1016/j.engfailanal.2015.02.017http://doi.org/10.1016/j.engfailanal.2015.02.017

L.Y. Chu, Experiment and numerical analysis of axial elastic and plastic buckling of welded cylindrical shells, Ph. D. Thesis, Zhe Jiang university (2012)

H. Qian, The analysis on elastic and plastic stability of cylindrical shell, Master Thesis, Wuhan University of Technology (2002)

X.G. Chen, Numerical buckling analysis and optimization of cylindrical shell under uniform axial compression, Ph. D. Thesis, Beijing University of Technology (2009)

Z. Yang, G.T. Jin, Stability design of axially compressed the cylindrical shells, Eng. Mech. 20, 116-126(2003). doi: 10.3969/j.issn.1000-4750.2003.06.021http://doi.org/10.3969/j.issn.1000-4750.2003.06.021

M. Imani, M. Aghaie, A. Zolfaghari et al., Numerical study of fuel-clad mechanical interaction during long-term burnup of WWER1000. Ann. Nucl. Energy. 80, 267-278(2015). doi: 10.1016/j.anucene.2015.01.036http://doi.org/10.1016/j.anucene.2015.01.036

A. Alemberti, J. Carlsson, E. Malambu et al., European lead fast reactor—ELSY, Nucl. Eng. Des. 241, 3470-3480(2011). doi: 10.1016/j.nucengdes.2011.03.029http://doi.org/10.1016/j.nucengdes.2011.03.029

H. Ju, Y. Ishiwatari, Y. Oka, Fuel rod behavior under normal operating conditions in Super Fast Reactor with high power density, Nucl. Eng. Des. 289, 166-174(2015). doi: 10.1016/j.nucengdes.2015.04.037http://doi.org/10.1016/j.nucengdes.2015.04.037

R.L. Williamson, J.D. Hales, S.R. Novascone et al., Multidimensional multiphysics simulation of nuclear fuel behavior, J. Nucl. Mater. 423,149-163(2012). doi: 10.1016/j.jnucmat.2012.01.012http://doi.org/10.1016/j.jnucmat.2012.01.012

J. Hofmeister, C. Waata, J. Starflinger et al., Fuel assembly design study for a reactor with supercritical water, Nucl. Eng. Des. 237, 1513-1521(2007). doi: 10.1016/j.nucengdes.2007.01.008http://doi.org/10.1016/j.nucengdes.2007.01.008

China Guangzhou Nuclear Power Engineering Co., Ltd. PWR nuclear island design 4th Vol. (Atomic Energy Press, Beijing, China, 2010), pp.55-56

G.S. Xie, R.X. Zhang, Fast neutron reactor fuel element. (Chemical Industry Press, Beijing, China, 2007), pp.54-129

H.A. Abderrahim, V. Sobolev, E. Malambu, et al., Fuel design for the experimental ADS MYRRHA, Technical Meeting on use of LEU in ADS. IAEA, (Viena, Austria, 2005), pp.1-13

ASME Boiler and Pressure Vessel Code, Section 2: Materials, Part D: Properties. (American Society of Mechanical Engineers, New York, USA, 2010), pp.707-744

S.M. Yang, W.Q. Tao, Heat transfer. (High Education Press, Beijing, China, 2007), pp.34-53

W.L. Huang, R.Y. Sa, D.N. Zhou, et al., Experimental study on fragmentation behaviors of molten LBE and water contact interface. Nucl. Sci. Tech. 2015, 26: 060601.doi: 10.13538/j.1001-8042/nst.26.060601http://doi.org/10.13538/j.1001-8042/nst.26.060601

Views

Downloads

CSCD

Alert me when the article has been cited

Submit

Tools

Publicity Resources

Avoiding sealing failure of flanged connection for tubes made of dissimilar materials subjected to elevated temperature

Related Author

No data

Related Institution

Shanghai Institute of Applied Physics, Chinese Academy of Sciences

Address：Editorial Office of NST, 2019 Jialuo Road, Jiading, Shanghai 201800, China Postal code：201800
Email：nst@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.

⁰