Published October 2015 | Version v1
Miscellaneous

Creep model for PWR spent nuclear fuel

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

After reactor operation spent nuclear fuel (SNF) has been stored in wet storage. The coolant temperature of wet storage is below 55℃ . Due to low temperatures, cladding creep is not activated. However, after wet storage, SNF transferred to dry storage. Initial peak cladding temperature in dry storage is known around 400oC. Therefore, cladding creep in dry storage has been considered as a main degradation mechanism which can bring a gross rupture of the cladding. In general, cladding creep in dry storage is recognized as a thermal creep because the fast neutron fluence is very low compare to in-reactor condition. In this work, we reviewed the creep model of PWR cladding material

Part of:
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2015

Additional details

Publishing Information

Publisher
KRS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2015
Imprint Pagination
542 p.
Journal Page Range
p. 101-102

Conference

Title
2015 Autumn Meeting of Korean Radioactive Waste Society
Dates
14-16 Oct 2015
Place
Daejeon (Korea, Republic of)

Optional Information

Notes
7 refs, 1 fig, 2 tabs