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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2008.1
- 수록면
- 21 - 36 (16page)
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초록· 키워드
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High burn-up fuel technology has been developed through a national R&D program, which covers key technology areas
such as claddings, UO2 pellets, spacer grids, performance code, and fuel assembly tests. New cladding alloys were developed
through alloy designs, tube fabrication, out-of-pile test and in-reactor test. The new Zr-Nb tubes are found to be much better
in their corrosion resistance and creep strength than the Zircaloy-4 tube, owing to an optimized composition and heat treatment
of the new Zr-Nb alloys. A new fabrication technology for large grain UO2 pellets was developed using various uranium
oxide seeds and a micro-doping of Al. The uranium oxide seeds, which were added to UO2 powder, were prepared by oxidizing
and heat-treating scrap UO2 pellets. A UO2 pellet containing tungsten channels was fabricated for a thermal conductivity
enhancement. For the fuel performance analysis, new high burnup models were developed and implemented in a code. This
code was verified by an international database and our own database. The developed spacer grid has two features of contoured
contact spring and hybrid mixing vanes. Mechanical and hydraulic tests showed that the spacer grid is superior in its rodsupporting,
wear resistance and CHF performance. Finally, fuel assembly test technology was also developed. Facilities for
mechanical and thermal hydraulic tests were constructed and are now in operation. Several achievements are to be utilized
soon by the Korea Nuclear Fuel and thereby contribute to the economy and safety of PWR fuel in Korea
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참고문헌 (31)
참고문헌 신청
Averty, X. / 2003 / Tensile tests on ring specimens machined in M5 cladding irradiated 6 cycles
B.E. Ingleby / 1986 / in: Fission-Product Behavior in Ceramic Oxide Fuel, Advances in Ceramics vol. 17 : 57 ~
C.B. Lee / 2004 / High Burnup UO2 Fuel Rod Performance Code INFRA / Proc. of the 2004 International Meeting on LWR Fuel Performance
C.B. Lee / 2004 / Post-irradiation Examination of High Burnup UO2 Fuel / Proc. of the 2004 International Meeting on LWR Fuel Performance
C.B. Lee / 2005 / INFRA Code Results of FUMEXII in : Improvement of models used for fuel behavior simulation (FUMEX-II)
B.E. Ingleby / 1986 / in: Fission-Product Behavior in Ceramic Oxide Fuel, Advances in Ceramics vol. 17 : 57 ~
C.B. Lee / 2004 / High Burnup UO2 Fuel Rod Performance Code INFRA / Proc. of the 2004 International Meeting on LWR Fuel Performance
C.B. Lee / 2004 / Post-irradiation Examination of High Burnup UO2 Fuel / Proc. of the 2004 International Meeting on LWR Fuel Performance
C.B. Lee / 2005 / INFRA Code Results of FUMEXII in : Improvement of models used for fuel behavior simulation (FUMEX-II)
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