Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage

Author:

Arkoma Asko,Huhtanen Risto,Leppänen Jaakko,Peltola Juho,Pättikangas Timo

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference45 articles.

1. Ansys, 2017. www.ansys.com/services/training-center/platform/introduction-to-ansys-icem-cfd-hexa (visited Nov. 1, 2017).

2. Bouffioux, P., 2005. Transportation and interim dry storage of PWR’s spent fuel. EDF report, HT25-C2005-192/PBF.

3. Bouffioux, P., Leclercq, S., Cappelaere, C., Bredel, T., 2001. Interim dry storage of PWR spent fuel assemblies – development of a long term creep law to assess the fuel cladding integrity. In: Proceedings of: 8th international conference on radioactive waste management and environmental remediation (ICEM’01), Bruges, Belgium, Sep. 30 – Oct. 4, 2001.

4. Impact of hydrogen on plasticity and creep of unirradiated Zircaloy-4 cladding tubes. In: Proceedings of: Zirconium in the nuclear industry, 12th international symposium;Bouffioux;ASTM STP,2000

5. Burkardt, J., 2013. Normal Random Number Generators. http://people.sc.fsu.edu/~jburkardt/f_src/normal/normal.html (visited March 29, 2018).

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