• Home
  • Browse
    • Current Issue
    • By Issue
    • By Author
    • By Subject
    • Author Index
    • Keyword Index
  • Journal Info
    • About Journal
    • Aims and Scope
    • Editorial Board
    • Editorial Staff
    • Publication Ethics
    • Indexing and Abstracting
    • Related Links
    • FAQ
    • Peer Review Process
    • News
  • Guide for Authors
  • Submit Manuscript
  • Reviewers
  • Contact Us
 
  • Login
  • Register
Home Articles List Article Information
  • Save Records
  • |
  • Printable Version
  • |
  • Recommend
  • |
  • How to cite Export to
    RIS EndNote BibTeX APA MLA Harvard Vancouver
  • |
  • Share Share
    CiteULike Mendeley Facebook Google LinkedIn Twitter
ADMT Journal
Articles in Press
Current Issue
Journal Archive
Volume Volume 11 (2018)
Issue Issue 4
Issue Issue 3
Issue Issue 2
Issue Issue 1
Volume Volume 10 (2017)
Volume Volume 9 (2016)
Volume Volume 8 (2015)
Volume Volume 7 (2014)
Volume Volume 6 (2013)
Volume Volume 5 (2011-2012)
Volume Volume 4 (2010-2011)
Volume Volume 3 (2009-2010)
Volume Volume 2 (2008-2009)
Volume Volume 1 (2007-2008)
bahonar, M., Jahanfarnia, G., Gharib, M. (2018). Preliminary Analysis of the Cladding Mechanical Behavior of a Nuclear Superheat Boiling Water Reactor. ADMT Journal, 11(2), 39-45.
majid bahonar; Gholamreza Jahanfarnia; Morteza Gharib. "Preliminary Analysis of the Cladding Mechanical Behavior of a Nuclear Superheat Boiling Water Reactor". ADMT Journal, 11, 2, 2018, 39-45.
bahonar, M., Jahanfarnia, G., Gharib, M. (2018). 'Preliminary Analysis of the Cladding Mechanical Behavior of a Nuclear Superheat Boiling Water Reactor', ADMT Journal, 11(2), pp. 39-45.
bahonar, M., Jahanfarnia, G., Gharib, M. Preliminary Analysis of the Cladding Mechanical Behavior of a Nuclear Superheat Boiling Water Reactor. ADMT Journal, 2018; 11(2): 39-45.

Preliminary Analysis of the Cladding Mechanical Behavior of a Nuclear Superheat Boiling Water Reactor

Article 4, Volume 11, Issue 2, Spring 2018, Page 39-45  XML PDF (740.97 K)
Document Type: Original Article
Authors
majid bahonar1; Gholamreza Jahanfarnia 2; Morteza Gharib2
1Department of Nuclear Engineering, Science and Research branch, Islamic Azad University, Tehran, Iran
2Department of nuclear engineering,science and research branch
Abstract
In the present study, investigation of mechanical behaviour of the fuel cladding material for a nuclear superheat Boiling Water Reactor with annular fuel rods, is carried out. In this design, each annular fuel element is cooled internally by steam and externally by water. For the fuel cladding material, radiation embitterment and irradiation-assisted stress corrosion cracking (IASCC) are the most important issues that have to be taken into account. Hence, for cladding, two materials are considered. Preliminary thermal expansion and stress analysis have been done for a fresh (begin of cycle) ASBWR (Annular-fuelled Superheat Boiling Water Reactor) fuel element. The purpose of these analysis is to investigate the stress distribution and thermal expansion of the cladding in the initial phase of operation. The results show that there is a noticeable difference in the axial expansion between the inner and outer claddings. For T91 (modified 9Cr-1Mo steel) cladding, the maximum axial thermal growth of the inner cladding is 22.12 mm, which is about 9.7 mm more than the outer cladding. For Inconel 718 cladding, the results are     27.8 mm and 13.4 mm, respectively.
Keywords
Annular fuel; strain; stress; Superheat BWR; Thermal expansion
Main Subjects
Mechanical Engineering
References
[1]     Novick, M., et al., Developments in Nuclear Superheat, Proceedings of the Third International Conference on the Peaceful Uses of Atomic Energy, Geneva, Aug. 31, Sep. 9, 1964.

[2]     Chih Ko, Yu., Conceptual Design of an Annular-Fueled Superheat Boiling Water Reactor, MIT Ph.D Thesis, Jun. 2010.

[3]     Sapundjiev, D., Al Mazouzi, A., and Van Dyck, S., A Study of the Neutron Irradiation Effects on the Susceptibility to Embrittlement of A316L and T91 Steels in Lead-Bismuth Eutectic, Journal of Nuclear Materials, Vol. 356, No. 1-3, Sep. 2006, pp. 229-236.

[4]     Chen, ., Sridharan, K., and Allen, T., Corrosion Behavior fferritic-Martensitic Steel T91 in Supercritical Water, Corrosion Science, Vol. 48, No. 9, 2006, pp. 2843-2854.   

[5]     Fazzolae, R., Gas-Cooled Fast Breeder Reactor Designs with Advanced Fuel and Cladding, Nuclear Engineering and Design, Vol. 40, No. 1, Jan. 1977, pp. 191-201.

[6]     Incone 718 Properties, On-line Resource, Available from World Wide Web: http://www.espimetals.com/tech/inconel7l8.pdf http://www.espimetals.com/technicaldata.htm

[7]     Ashrafi Nik, M., Dec. Thermo Hydraulic Optimization of the EURISOL DS Target, No. 2, TM-34-06-04, 2006.

[8]     Harvey, J. F., Theory and Design of Pressure Vessels, Springer, Sep. 1991.

Statistics
Article View: 348
PDF Download: 152
Home | Glossary | News | Aims and Scope | Sitemap
Top Top

Address: Mechanical Engineering Department, Majlesi Branch, Islamic Azad University, Isfahan, Iran. Postal Code: 8631656451

Tel: (+98)31-52472290 ext. 232 - Email: jmechanic@iaumajlesi.ac.ir

All Rights Reserved. © 2007-2015 Islamic Azad University, Majlesi Branch.

Journal Management System. Designed by sinaweb.