Published 2016 | Version v1
Book

Hydride effects on discharged fuel clad related to accident conditions during dry storage and handling - 2016-0043

Description

Safe handling of nuclear reactor discharged fuel requires an understanding of how the fuel (cladding) will perform under the various encountered conditions, including off-normal events, such as drop events in handling the storage canister. Clad failures under two distinct loading modes are considered: a diametrical pinch mode and an axial-bend mode. The mechanical response to the pinch mode and the bend mode loading are evaluated with ring compression testing (RCT) and three-point bend (TPB) testing, respectively. ZIRLOR clad samples were hydrogen charged to levels from 100 ppm to 800 ppm and then subjected to a hydride reorientation treatment involving heating to 400 deg. C and cooling while under hoop stresses ranging from 90 MPa to 170 MPa. Radial hydride reorientations were characterized and RCT and TPB tests were performed over a temperature range of ambient to 200 deg. C. Ductile-to-brittle transition temperatures (DBTT) were determined. Using finite element analysis (FEA), true stresses and strains are calculated and comparisons made between the RCT and TPB test modes. Because of the anisotropic properties of the clad and the relative orientation and generic effects of the hydrides, the DBTT was observed to be strongly dependent on the mode of strain application such that a DBTT associated with an RCT test is different from a DBTT obtained using an axial-bend test. Although the degree of radial hydriding strongly affected the pinch-mode RCT test, the same radial hydride impact was not observed for the axial-bend TPB test, which was affected strongly by the bulk hydride levels and not by the fraction of radial hydrides. (authors)

Availability note (English)

Available from doi: http://dx.doi.org/10.1520/STP159720160043

Additional details

Identifiers

Publishing Information

Publisher
ASTM International
Imprint Place
West Conshohocken, PA (United States)
Imprint Pagination
32 p.

Conference

Title
18. International Symposium on Zirconium in the Nuclear Industry
Dates
15-19 May 2016
Place
Hilton Head, SC (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
50032042
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPRESSION; CONTAINERS; COOLING; DRY STORAGE; DUCTILE-BRITTLE TRANSITIONS; FAILURES; HEATING; MECHANICAL TESTS; PRESSURE RANGE MEGA PA; SPENT FUELS; STRAINS; STRESSES; TRANSITION TEMPERATURE
Descriptors DEC
ENERGY SOURCES; FUELS; MATERIALS; MATERIALS TESTING; NUCLEAR FUELS; PHYSICAL PROPERTIES; PRESSURE RANGE; REACTOR MATERIALS; STORAGE; TESTING; THERMODYNAMIC PROPERTIES

Optional Information

Notes
11 refs.