Publications
Showing 71 results for Author: Ben E. Garrison
Nov, 2023
ORNL Report
Sister Rod Destructive Examinations (FY22) Appendix E: Mechanical Testing
As a part of the DOE NE High Burnup Spent Fuel Data Project, Oak Ridge National Laboratory (ORNL) is performing destructive examinations (DEs) of high burnup (HBU) (>45 GWd/MTU) spent nuclear fuel (SNF) rods from the North Anna Nuclear Power Station operated by Dominion Energy. The SNF rods, called sister rods or sibling rods, are all HBU and include four different kinds o…
Nov, 2023
Journal
Nondestructive hydrogen analysis of steam-oxidized Zircaloy-4 by wide-angle neutron scattering
A nondestructive neutron scattering method to precisely measure the hydrogen content in high-temperature steam-oxidized Zircaloy-4 cladding was developed. Zircaloy-4 cladding was used to produce hydrided specimens with hydrogen content up to ≈500 wppm. Following hydrogen charging, the hydrogen content of the hydrided specimens was measured using the vacuum hot extraction m…
Nov, 2023
Journal
Determining failure properties of as-received and hydrided unirradiated Zircaloy-4 from ring compression tests
An integrated experimental and computational approach was developed to determine the plastic strain at fracture and to investigate the fracture energy of as-received and hydrided unirradiated Zircaloy-4 nuclear cladding tubes in the hoop direction at room temperature from ring compression testing (RCT). This work builds on previous methods in the literature that were devel…
Nov, 2023
ORNL Report
POST-QUENCH DUCTILITY STUDY OF ARMOR COATED AND UNCOATED ZIRCALOY-2 TUBING SPECIMENS
Nov, 2023
ORNL Report
Progress Report on Modified Burst Testing and Alternative Test Methodologies
Performance of accident-tolerant fuel candidates must be assessed during the pellet-cladding mechanical interaction (PCMI) phase of a design-basis reactivity-initiated accident (RIA). Therefore, in this report, we describe Fiscal Year (FY) 2019 research activities on the development of separate-effects testing for ATF cladding candidate iron-chromium-aluminum (FeCrAl) tube…
Nov, 2023
Journal
Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions
The reactivity initiated accident (RIA) is a postulated accident in light water reactors initiated by a rapid increase in reactivity which causes an increase in fission rate and fuel temperature. One potential mode of fuel system failure during RIA is pellet cladding mechanical interaction (PCMI) due to the rapid thermal expansion of the fuel pellet. Simulated PCMI experim…