Published June 2013 | Version v1
Report

New Techniques for the Testing of Cladding Material under RIA Conditions

  • 1. Electric Power Research Institute, Charlotte (United States)
  • 2. Westinghouse Electric Company, Monroeville (United States)
  • 3. Studsvik Nuclear AB, Nykoeping (Sweden)
  • 4. Maxbar, Inc. Houston (United States)
  • 5. Global Nuclear Fuel, Wilmington (United States)
  • 6. Vattenfall Nuclear Fuel, Stockholm (Sweden)

Description

Two new mechanical tests, rapid heating and loading (RHL) and modified burst, have been developed to evaluate cladding properties under RIA heating and loading conditions. The RHL test was designed to evaluate cladding ductility changes due to temperature increases during a RIA. A series of RHL tests were conducted using pre-hydrided and irradiated cladding. The test samples were heated to different target temperatures from ambient to 350oC and simultaneously loaded to failure within 70 ms. Both non-irradiated and irradiated material test results conclusively show ductility is immediately recovered as the temperature is increased. A brittle-toductile transition, between 75oC and 100oC, was observed for both non- and irradiated Zircaloy-2 materials. The instantaneous ductility recovery also suggests that rapid heating should not be required in the evaluation of ductility degradation due to hydrides under RIA loading conditions. A modified burst test was developed to mechanical simulate the loading conditions of a RIA. The test uses a driver tube with a gauge section and loading is provided via a piston/cylinder arrangement which allow for greater control of the sample deformation. The configuration allows for total control of the pressure pulse duration as well as desired diameter deformation. A number of tests have been conducted using cold-worked, cold-worked and hydrogen charged, and irradiated cladding material. The test results verify ductility recovery as observed in the RHL test and post-test measured plastic strain at failure is comparable and consistent with NSRR test results at ambient and elevated temperatures. (author)

Part of:
Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions. Proceedings of a Technical Meeting

Additional details

Publishing Information

ISBN
978-92-0-192410-0
Imprint Title
Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions. Proceedings of a Technical Meeting
Imprint Pagination
398 p.
Journal Page Range
p. 55-65
ISSN
1684-2073
Report number
IAEA-TECDOC-CD--1709

Conference

Title
Technical Meeting on Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions
Dates
18-21 Oct 2011
Place
Mito (Japan)

Optional Information

Notes
14 figs., 1 tab., 4 refs.