Published 2017 | Version v1
Miscellaneous

Assesment of nue fuel element performance in normal operating conditions

  • 1. RATEN Institute for Nuclear Research, Pitesti (Romania)
  • 2. University of Pitesti (Romania)

Description

Due to its neutron economy, versatility of fuel channel and simplicity of fuel bundle design, CANDU reactors have a unique ability of efficiently using alternative fuel, such as: depleted uranium (DU), recycled uranium (RU), mixed oxide of Thorium and Plutonium ((Pu,Th)MOX) and natural uranium equivalent (NUE). This paper outlines the results on the investigation of two analysed cases (NUE versus 37S) with ELESIM computer code, aimed to evaluate the fuel behaviour in normal operating conditions. ELESIM computer code estimates the nuclear fuel elements performance parameters, for a given history power, using one-dimensional models for heat generation, temperature distribution, fission gas release and pellet to sheath heat transfer. The fuel bundle power distribution respectively for each ring corresponding to a fuel channel was obtained with LEGENTR3D, WIMS and DRAGON programs. (authors)

Part of:
Proceedings of NUCLEAR 2017 international conference on sustainable development through nuclear research and education. Part 3/3

Additional details

Publishing Information

Publisher
Institute for Nuclear Research - Pitesti
Imprint Place
Pitesti (Romania)
Imprint Title
Proceedings of NUCLEAR 2017 international conference on sustainable development through nuclear research and education. Part 3/3
Imprint Pagination
129 p.
Journal Page Range
p. 65-71
ISSN
2066-2955
Report number
INIS-RO--0014

Conference

Title
10. annual international conference on sustainable development through nuclear research and education
Acronym
NUCLEAR 2017
Dates
24-26 May 2017
Place
Pitesti (Romania)

Optional Information

Notes
6 figs., 3 tabs.