Published 2016 | Version v1
Book

A study on the assessment criteria of DHC in PWR spent fuel

  • 1. LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, 34057 (Korea, Republic of)

Description

One of the major degradation mechanisms of PWR spent fuel cladding is delayed hydride cracking (DHC), which can activate within a relatively low temperature range. Its maximum crack growth rate is estimated to be within the range of 10-7 m/s, at which the cladding can rupture in 1 to 2 years during dry storage. For this reason, it is essential to prevent DHC crack growth itself, but most of the existing DHC studies have been focused on the crack growth rate. In this regard, the values and characteristics of the threshold stress intensity factor (KIH) for PWR Zircaloy-4 cladding were described. Based on the limited existing test results and analysis, the experimentally measured KIH were compared with the predicted KIH. The comparison shows that the predicted values are much lower than the measured ones and both theoretical estimation and measured values of KIH increase as the temperature increases. The possibilities of degradation by DHC were also discussed during long-term dry storage. For a more reliable analysis, additional information on a pre-existing crack of spent fuel is needed

Availability note (English)

Available from: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US), also available in CD-Rom
Part of:
Top Fuel 2016 Proceedings

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
ISBN
978-0-89448-734-7
Imprint Title
TOP FUEL 2016 Proceedings
Imprint Pagination
1670 p.
Journal Page Range
p. 557-561

Conference

Title
LWR fuels with enhanced safety and performance
Acronym
TOP FUEL 2016
Dates
11-15 Sep 2016
Place
Boise, ID (United States)

Optional Information

Notes
7 refs.