Published 1991 | Version v1
Report

An improved model for cladding strain intensification over radial cracks in nuclear fuel pellets

  • 1. UKAEA Harwell Lab. (United Kingdom). Theoretical Physics Div.
  • 2. Imperial College of Science and Technology, London (United Kingdom). Department of Mechanical Engineering

Description

The opening of radial cracks in fuel pellets can cause strains in adjacent cladding to be large, as frictional forces inhibit relative movement between the pellet and the cladding. An analytical model of this strain intensification process is presented. This model, more rigorous than previously published approaches, explicitly accounts for strain concentration only over part of the cladding perimeter. The azimuthal extent of slipping at the fuel-cladding interface is calculated and the effect of external pressure and any prior uniform clad strain is included. Numerical results are presented for sample cases and the coupling of the model to fuel performance codes is described

Part of:
Transactions of 2. international seminars on the mathematical/mechanical modelling of reactor fuel elements

Additional details

Publishing Information

Imprint Title
Mathematical/Mechanical Modelling of Reactor Fuel Elements
Imprint Pagination
276 p.
Journal Page Range
p. 119-146.
Report number
EUR--13660

Conference

Title
2. International Seminars on the Mathematical/Mechanical Modelling of Reactor Fuel Elements.
Dates
21-22 Aug 1989.
Place
La Jolla, CA (United States).

INIS

Country of Publication
European Commission (EC), Brussels (Belgium)
Country of Input or Organization
European Commission (EC), Brussels (Belgium)
INIS RN
23026194
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANALYTICAL SOLUTION; CRACKS; FUEL PELLETS; FUEL RODS; FUEL-CLADDING INTERACTIONS; STRAIN RATE
Descriptors DEC
FUEL ELEMENTS; REACTOR COMPONENTS

Optional Information