Published May 2015 | Version v1
Miscellaneous

Development of Enhanced Accident Tolerant LWR Fuel Cladding

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

Description

In comparison with the standard UO2-Zr alloy system which is currently used in the LWRs, enhanced accident tolerance fuels (ATF) can tolerate loss of active cooling in reactor core for a considerably longer time period during design-basis and beyond design-basis event while maintaining or improving the fuel performance during normal operations and operational transients. As the ATF cladding concepts, coating cladding, Mo-Zr cladding, FeCrAl cladding, and SiC/SiCf cladding have being developed in many countries. Regarding the cladding performance, new fuel cladding concepts will be evaluated with respect to the accident scenarios and specific plant designs for LWRs and fuel cladding fabrication facilities. After the consideration of various performances in accident and normal conditions, the coating cladding concept was selected to apply an ATF cladding in this study. A surface modified cladding as a new concept is suggested to apply an enhanced accident tolerance fuel cladding. The key technologies of new concept were consisted of the partial ODS treatment and surface coating. The aim of the partial ODS treatment is to increase the high temperature strength to suppress the ballooning/rupture behavior of fuel cladding during accident event. The target of the surface coating is to increase the corrosion resistance during normal operation condition and to increase the oxidation resistance during accident event

Part of:
Proceedings of the KNS 2015 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2015 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2015 spring meeting of the KNS
Dates
6-8 May 2015
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47023153
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CLADDING; COOLING; CORROSION RESISTANCE; DESIGN; FABRICATION; PERFORMANCE; REACTOR CORES; URANIUM DIOXIDE; WATER COOLED REACTORS
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; DEPOSITION; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
2 refs, 1 fig