Published October 2014 | Version v1
Miscellaneous

End Closure Welding of SFR Metallic Fuel Rod by GTAW

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

Description

The Gen-IV program was started by eleven countries from 2000 for the development of innovative nuclear energy system with the goals, safety, economics, resource utilization, waste management, proliferation resistance and physical protection (PR-PP). The sodium-cooled fast reactor (SFR) system is among the six systems selected for Gen-IV promising systems and expected to be deployed in 2020. For the fabrication of SFR metallic fuel rods, the end plug welding is a crucial process. The sealing of end plug to cladding tube should be hermetically perfect to prevent a leakage of fission gases and to maintain a good reactor performance. In this study, the welding technique, welding equipment, welding conditions and parameters were developed for the end closure of SFR metallic fuel rods. The gas tungsten arc welding (GTAW) technique was adopted and the welding joint design was developed. And the optimal welding conditions and parameters were established. For end closure welding of SFR metallic fuel rod, the welding technique, welding equipment, welding conditions and parameters were developed. The GTAW technique was adopted and the welding joint design was improved. And the optimal welding conditions and parameters were well established

Part of:
Proceedings of the KNS 2014 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2014 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2014 Fall Meeting of the KNS
Dates
29-31 Oct 2014
Place
Pyongchang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
46060671
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CLADDING; DESIGN; FUEL CYCLE; FUEL RODS; NUCLEAR ENERGY; SAFETY; SODIUM COOLED REACTORS; TUBES
Descriptors DEC
DEPOSITION; ENERGY; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; SURFACE COATING

Optional Information

Notes
7 refs, 6 figs, 1 tab