The aim of this paper is to provide an analytical determination of temperature and thermal stress in a cylindrical nuclear fuel rod with cladding, including the actual neutron flux distribution in a unit cell, fur a thermal reactor in steady state. The temperature and stresses are evaluated by solving a set of differential and integral equations, derived from the heat conduction and Hooke's law. Some numerical applications are presented (with reference to a common pressurized water reactor) and discussed. The emphasis is placed on the influence of nuclear parameters on the thermal and mechanical behavior of the fuel element.

Relationship between nuclear and thermomechanical aspects in fuel rod design / Spiga, Marco; Spiga, Giampiero. - In: JOURNAL OF THERMAL STRESSES. - ISSN 0149-5739. - 5:(3-4)(1982), pp. 377-394. [10.1080/01495738208942157]

Relationship between nuclear and thermomechanical aspects in fuel rod design

SPIGA, Marco;SPIGA, Giampiero
1982-01-01

Abstract

The aim of this paper is to provide an analytical determination of temperature and thermal stress in a cylindrical nuclear fuel rod with cladding, including the actual neutron flux distribution in a unit cell, fur a thermal reactor in steady state. The temperature and stresses are evaluated by solving a set of differential and integral equations, derived from the heat conduction and Hooke's law. Some numerical applications are presented (with reference to a common pressurized water reactor) and discussed. The emphasis is placed on the influence of nuclear parameters on the thermal and mechanical behavior of the fuel element.
1982
Relationship between nuclear and thermomechanical aspects in fuel rod design / Spiga, Marco; Spiga, Giampiero. - In: JOURNAL OF THERMAL STRESSES. - ISSN 0149-5739. - 5:(3-4)(1982), pp. 377-394. [10.1080/01495738208942157]
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11381/1508709
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