Detail publikace

Calculation of stress and deformation in fuel rod cladding during pellet-cladding interaction

HALABUK, D. MARTINEC, J.

Anglický název

Calculation of stress and deformation in fuel rod cladding during pellet-cladding interaction

Typ

článek v časopise ve Web of Science, Jimp

Jazyk

en

Originální abstrakt

The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main function of cladding is hermetic separation of nuclear fuel from coolant. The fuel rod works in very specific and difficult conditions, so there are high requirements on its reliability and safety. During irradiation of fuel rods, a state may occur when fuel pellet and cladding interact. This state is followed by changes of stress and deformations in the fuel cladding. The article is focused on stress and deformation analysis of fuel cladding, where two fuels are compared: a fresh one and a spent one, which is in contact with cladding. The calculations are done for 4 different shapes of fuel pellets. It is possible to evaluate which shape of fuel pellet is the most appropriate in consideration of stress and deformation forming in fuel cladding, axial dilatation of fuel, and radial temperature distribution in the fuel rod, based on the obtained results.

Anglický abstrakt

The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main function of cladding is hermetic separation of nuclear fuel from coolant. The fuel rod works in very specific and difficult conditions, so there are high requirements on its reliability and safety. During irradiation of fuel rods, a state may occur when fuel pellet and cladding interact. This state is followed by changes of stress and deformations in the fuel cladding. The article is focused on stress and deformation analysis of fuel cladding, where two fuels are compared: a fresh one and a spent one, which is in contact with cladding. The calculations are done for 4 different shapes of fuel pellets. It is possible to evaluate which shape of fuel pellet is the most appropriate in consideration of stress and deformation forming in fuel cladding, axial dilatation of fuel, and radial temperature distribution in the fuel rod, based on the obtained results.

Klíčová slova anglicky

fuel cladding, fuel rod, nuclear fuel, stress and deformation analysis

Vydáno

18.12.2015

Nakladatel

Czech Technical University in Prague

Místo

Praha

ISSN

1210-2709

Ročník

55

Číslo

6

Strany od–do

384–387

Počet stran

4

BIBTEX


@article{BUT139245,
  author="Dávid {Halabuk} and Jiří {Martinec},
  title="Calculation of stress and deformation in fuel rod cladding during pellet-cladding interaction",
  year="2015",
  volume="55",
  number="6",
  month="December",
  pages="384--387",
  publisher="Czech Technical University in Prague",
  address="Praha",
  issn="1210-2709"
}