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Hafnium in Nuclear Fuel Cladding Used Both as Oxidation Protection and Burnable Absorber

[+] Author Affiliations
Jiři Závorka, Radek Škoda

Czech Technical University, Prague, Czech Republic

Paper No. ICONE24-60302, pp. V005T15A015; 6 pages
  • 2016 24th International Conference on Nuclear Engineering
  • Volume 5: Student Paper Competition
  • Charlotte, North Carolina, USA, June 26–30, 2016
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5005-3
  • Copyright © 2016 by ASME


The problem with higher nuclear fuel enrichment is its high initial reactivity. It has a negative effect on the peaking factor, which is one of the license conditions. The second major problem is the ability to control the reactivity of the reactor, and thereby maintaining the multiplication factor in the core equal to 1. Long-term control of the reactivity in PWR reactors is typically conducted by the concentrated boric acid (H3BO3) in the coolant; its highest possible concentration is determined by the requirement to maintain a negative reactivity coefficient. Another option are burnable absorbers.

This work deals with usage of hafnium as an advanced type of burnable absorber. Based on the model of computing code UWB1 for the study of burnable absorbers, a new cladding of nuclear fuel is designed with a thin protective layer made of hafnium. This cladding is used as a burnable absorber that helps reducing excess of fuel reactivity and prolongs the life of the fuel assemblies, which increases economic coefficient of the use of nuclear power plants. This cladding would also work as a protective layer increasing endurance and safety of nuclear power plants. Today zirconium alloys are exclusively used for this purpose. The main disadvantages of zirconium alloys include rapid high temperature oxidation of zirconium — a highly exothermic reaction between zirconium and water steam at temperatures above 800 °C. During this reaction hydrogen and inconsiderable amount of heat are released. Hydrogen excess, released heat, and damaged cover of fuel may deepen the severity and consequences of possible accidents. Another disadvantage of zirconium alloys is their gradual oxidation under standard operating conditions and ZrH formation, which leads to cladding embrittlement.

Copyright © 2016 by ASME



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