Published March 2018 | Version v1
Miscellaneous

Fuel integrity evaluation during the dry storage by FRAPCON

  • 1. Dept. of Nuclear Engineering, Kyung Hee University, Yongin (Korea, Republic of)

Description

Regulatory commission limits the cladding temperature to 400 degrees C for fuel with a burnup greater than 45 GWD/MTU. The 400 degrees C is set to prevent damage of the fuel rod cladding and the dry storage cask components related to high temperature. Also, it is important to analyze the hoop stress and determine if it remains below the 90 MPa for hydride reorientation in high-burnup fuel. Recently, David j. Richmond shows that the hoop stress may be related to the axial cladding temperature and oxidation profiles of the rods as well as the rod internal pressure at the end of life and in storage. The aim of this paper is to predict spent fuel integrity evaluation such as the axial cladding temperature and the hoop stress in the dry storage. To predict the cladding temperature and hoop stress of spent fuel is very important for integrity evaluation during the dry storage. The axial temperature and hoop stress during dry storage will give information such as the weakest location.

Part of:
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018

Additional details

Publishing Information

Publisher
KRS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018
Imprint Pagination
426 p.
Journal Page Range
p. 74-75

Conference

Title
2018 Spring Meeting of Korean Radioactive Waste Society
Dates
30 Mar 2018
Place
Daejeon (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50066593
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BURNUP; CASKS; DRY STORAGE; FUEL INTEGRITY; FUEL RODS; OXIDATION; REGULATIONS; SPENT FUELS; STRESSES
Descriptors DEC
CHEMICAL REACTIONS; CONTAINERS; ENERGY SOURCES; FUEL ELEMENTS; FUELS; LAWS; MATERIALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; STORAGE

Optional Information

Notes
4 refs, 4 figs, 2 tabs