Published 2007 | Version v1
Miscellaneous

Technical Challenges for a Dual-Cooling Fuel Structural Components

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

Description

This paper introduces mechanical component issues of a new concept PWR fuel, which is named as a 'Dual- Cooling Fuel'. The key feature of the dual-cooling fuel is readily discriminated by its annular cross-section of a fuel rod. So to speak, the fuel rod has an internal coolant passage in addition to an external one so that a fuel rod consists of coaxial inner and outer cladding tubes in which donut-shaped pellets are stacked. An intrinsic purpose of this shape is to increase the surface area of heat transfer which results in a reduction of the fuel temperature. The important effects of this idea are to enhance the fuel safety and to achieve a power uprating. This idea has been recently studied at Massachusetts Institute of Technology (MIT) for about 3-4 years. They picked up a conventional 17x17 PWR fuel of the Westinghouse type as a candidate and changed it into a 13x13 array fuel with increasing the outer diameter and making an additional internal flow passage. They found that the power uprating can be achieved by 50% with upgrading some necessary components of a nuclear power plant. Fuel performance, safety analysis and pellet fabrication were dealt with in their study but the fuel mechanical components have not been considered. PWR fuel development division of Korea Atomic Energy Research Institute (KAERI) recently started a new project of developing a above-mentioned fuel technology through a National R and D Program by the Ministry of Science and Technology. One of the relevant projects is to develop a design technology of the major structural components of a double-cooling fuel. As for the components, fuel rod supporting structure, top and bottom end pieces, guide thimbles and instrumentation tube were chosen. Differently than the MIT's works, the dual-cooling fuel components have to be compatible with the OPR 1000 system without replacing the reactor internals. Therefore, many challenging problems have to be tackled in this project. This paper describes some of the key issues that should be resolved

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2007 spring meeting of the KNS
Dates
10-11 May 2007
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38113297
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING; CROSS SECTIONS; FUEL RODS; PERFORMANCE; PWR TYPE REACTORS; SAFETY ANALYSIS
Descriptors DEC
ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 1 fig