Modal Analysis of Spent Fuel Cask for WWER-1000 Reactors

Authors

  • A. Kazemi Nuclear Power Production and Development Co. of Irna, AEOI, P.O. Box: 19395-7484, Tehran - Iran
  • S.A. Azimfar Nuclear Power Production and Development Co. of Irna, AEOI, P.O. Box: 19395-7484, Tehran - Iran
Abstract:

The Spent Fuel Assemblies (SFAs) of WWER-1000 reactors are planned to be transported by special containers which are supposed to be designed in a manner to stand against vibrations and impacts in order to protect the spent fuel from any possible damage. The vibration opposition of these containers shall be far beyond the critical resonance, because the resonances about the natural frequency of the structure will cause the enhancement of its oscillation range and may end with its disintegration. Determination of the amounts of natural frequencies and their mode shape can be achieved by vibration analyzing methods. The amount of the natural frequency of any structure crucially depends on its shape, material and lean points as well as the amount of the loads and the type of these loads. Due to the fact that the Spent Fuel Casks used for transportation in nuclear power plants in Russian Federation are TK-13 type and the pieces of information released are negligible, the scientists in Russia are working on the design and analysis of a new type made up of composite Material. In the presented paper the cask of spent fuel of TK-13 is modeled by ANSYS® 10.0 and ten natural frequency modes have been calculated, followed by the comparison of this result with the composite cask.

Upgrade to premium to download articles

Sign up to access the full text

Already have an account?login

similar resources

Potential Radioactive Releases from Commercial Reactors and Spent Fuel*

Commercial nuclear reactors and storage facilities for their spent fuel contain large amounts of radioactive material, and are not designed to resist attack. The US Nuclear Regulatory Commission (NRC) has determined, however, that these facilities require only a light defense. This paper shows, without disclosing any sensitive information, that reactors and spent-fuelstorage facilities have vul...

full text

Investigation of the required thickness of thorium spent fuel lead transport cask depending on different fuel burnups and cooling times

Thorium fuels have attracted researcher’s attention due to the reduction of uranium deposits in the world, more abundances than uranium, and the ability to be breeding in thermal and fast reactors. This study aimed to investigate the radiation safety and the amount of necessary shielding for the transportation of spent thorium fuel in the Tehran Research Reactor. The ORIGEN and MCNPX computatio...

full text

Monitoring and Leak testig of wwer-440 fuel assemblies in Slovak wet interim spent fuel storage facility

Monitorovanie a únik testovanej WWER – 440 látky namočenej do vyčerpaného paliva zo skladu sústredenom na Slovensku An accelerated monitoring system designed for the Slovak wet interim spent fuel storage facility in NPP Jaslovské Bohunice bases on the newly designed “cesium detectors” is presented in the paper. Since 1999, leak tests of WWER-440 fuel assemblies are provided by a special leak ti...

full text

shielding and criticality safety analyses for spent fuel transportation cask in tehran research reactor

in this research, shielding and criticality safety calculations carried out for interim storage and transportation cask in the tehran research reactor. such dual purpose cask is being designed to the spent fuel elements of research reactors. the monte carlo mcnp5 code calculation was utilized for the criticality safety analysis and origen2.1code was used for shielding calculation. according to ...

full text

Safety Analysis of Spent Fuel Transportation Cask of Bushehr Nuclear Power Plant through the Passing of Fire Tunnel with ANSYS®10.0

The spent fuel assemblies (FAs) of Bushehr Nuclear Power Plant are planed to be transported by TK-13 casks. Each spent fuel transportation cask holds 12 spent FAs and has a thick steel container to provide shielding. The calculations have been performed for FAs with burn ups of 60 MWd/kg and a 3-years cooling period. The ANSYS®10.0 general finite element analysis package was se...

full text

BULK GaAs-BASED NEUTRON DETECTORS FOR SPENT FUEL ANALYSIS

Bulk GaAs-based B coated detectors are under investigation as potential devices to assist in transmission analysis of spent nuclear fuel elements. The GaAs detectors are presently being investigated for their radiation hardness, neutron sensitivity and gamma ray insensitivity. The devices are to be used for evaluation, at first, with thermal neutrons, and later with 24 keV neutrons. Preliminary...

full text

My Resources

Save resource for easier access later

Save to my library Already added to my library

{@ msg_add @}


Journal title

volume 32  issue جلد 56

pages  50- 54

publication date 2011-08-23

By following a journal you will be notified via email when a new issue of this journal is published.

Hosted on Doprax cloud platform doprax.com

copyright © 2015-2023