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Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes

Journal Article · · Nuclear Technology
 [1];  [2]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States); Univ. of California, Berkeley, CA (United States)
Here, this work is motivated by the desire to devise an internal pressure test that can mimic a displacement-controlled loading scenario and demonstrate how to apply the multiaxial stress and strain data from the test to develop an elastic/plastic constitutive model for a thin-walled tubular component. This is achieved by conducting simultaneous measurements of tangential and axial strain during the pressure test and integrating these strain measures into a feedback loop with the pressure controller. It is shown how data from such a test can be used to develop a large mechanical property data set relevant to biaxial loading conditions. The data obtained have high confidence evidenced by their low variability and alignment with other literature studies. Additionally, data from these internal pressure tests combined with full-tube axial tensile tests allow for the derivation of the Hill anisotropic yield function. The developed Hill yield function is validated by comparing the plastic strain ratios from the full-tube tension tests and by comparing the predicted yield stress in the tangential direction with measured values from ring tension tests in a previous study.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1961539
Report Number(s):
INL/JOU-22-68523-Rev000
Journal Information:
Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 6 Vol. 209; ISSN 0029-5450
Publisher:
Taylor & FrancisCopyright Statement
Country of Publication:
United States
Language:
English

References (28)

Creep of zirconium and zirconium alloys journal August 2006
Poisson's ratio in zircaloy-4 between 24° and 316°C journal April 1978
A review of microstructure evolution in zirconium alloys during irradiation journal October 1988
Effect of hydrogen contents on the mechanical properties of Zircaloy-4 journal January 1994
Transient Response of LWR Fuels (RIA) book January 2012
The properties of the ring and burst creep of ZIRLO cladding journal April 2006
On the method to obtain the elastic properties using a pressurized thin tube journal April 2020
Determining failure properties of as-received and hydrided unirradiated Zircaloy-4 from ring compression tests journal July 2021
On mechanical response of Zircaloy-4 under a wider range of stress states: From uniaxial tension to uniaxial compression journal December 2020
Effect of uniaxial loading direction on mechanical responses and texture evolution in cold pilgered Zircaloy-4 tube: Experiments and modeling journal March 2021
A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditions journal August 2008
Mechanical behavior of recrystallized Zircaloy-4 under monotonic loading at room temperature: Tests and simplified anisotropic modeling journal April 2014
Fuel cladding behavior under rapid loading conditions journal February 2016
Applicability of modified burst test data to reactivity initiated accident journal May 2017
Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature journal January 2022
A study on texture stability and the biaxial creep behavior of as-hydrided CWSR Zircaloy-4 cladding at the effective stresses from 55 MPa to 65 MPa and temperatures from 300 °C to 400 °C journal June 2022
Fracture of Zircaloy-4 cladding tubes with or without hydride blisters in uniaxial to plane strain conditions with standard and optimized expansion due to compression tests journal May 2014
Effects of hydrogen contents on the mechanical properties of Zircaloy-4 sheets journal April 2016
Texture development and mechanical behavior of Zircaloy-4 alloy plates fabricated by cold rolling and annealing journal March 2021
Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes journal June 2022
Improved-EDC tests on the Zircaloy-4 cladding tube with an outer surface pre-crack journal December 2015
Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions journal December 2004
Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test journal January 2005
Single-Crystal Elastic Moduli and the hcp → bcc Transformation in Ti, Zr, and Hf journal July 1964
Analysis of Pellet-Clad Mechanical Interaction Process of High-Burnup PWR Fuel Rods by RANNS Code in Reactivity-Initiated Accident Conditions journal September 2006
Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions book January 2002
Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N. S. Savannah Reactor Design report July 1962
PNNL Stress/Strain Correlation for Zircaloy report July 2008

Figures / Tables (15)