• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.05a
• /
• pp.211.1-211
• /
• 2002

• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.05a
• /
• pp.335.2-335
• /
• 2002

• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.05a
• /
• pp.266.1-266.1
• /
• 2004

• Proceedings of the Korean Nuclear Society Conference
• /
• 2001.10a
• /
• pp.123-123
• /
• 2001

• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.10a
• /
• pp.241.2-241
• /
• 2002

• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.10a
• /
• pp.299-299
• /
• 2002

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2016.10a
• /
• pp.181-182
• /
• 2016

• Proceedings of the Korean Nuclear Society Conference
• /
• 1995.05a
• /
• pp.693-698
• /
• 1995

원자로 조사 핵연료의 제원거동을 조사하기 위하여 고리원자력1호기 핵연료(평균연소도:17,000-38,000MWD/MTU, 농축도: 2.122-3.199 wt.%) 대한 제원을 측정하였다. 핵연료 연소도에 따른 핵연료봉의 길이신장률과 집합체 길이신장률이 각각 0.4-0.6sc, 0.1-0.2%였다. 조사 핵연료의 길이신장과 핵연료 집합체의 휨은 주로 핵연료 연소도에 의존하였으나 핵연료집합체의 비틀림은 핵연료 연소도와 거의 무관하였다.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.12 no.1
• /
• pp.11-16
• /
• 2016

Fuel assembly's mechanical characterization test facility (FAMeCT) in KAERI was constructed with upgraded functional features such as increased loading capacity, underwater vibration testing and severe earthquake simulation for extended fuel design guideline. This facility is designed and developed to provide out-pile fuel data for accident analysis model and fuel licensing. Functional tests of FAMeCT were performed to confirm functionality, structural integrity, and validity of newly-built fuel assembly mechanical test facility. Test program includes signal check of data acquisition system, load delivering capacity using real-sized fuel assemblies and a standard loading cylindrical rigid specimen. Fuel assembly's lateral bending test was carried out up to 30 mm of pull-out displacement. Limit case axial compression loading test up to 33 kN was performed to check structural integrity of UCPS (Upper Core Plate Simulator) support frame. Test results show that all test equipment and measurement system have acceptable range of alignment, signal to noise ratio, load carrying capacity limit without loss of integrity. This paper introduces newly constructed fuel assembly's mechanical test facility and summarizes results of functional test for the mechanical test equipment and data acquisition system.

• Journal of the Computational Structural Engineering Institute of Korea
• /
• v.18 no.4 s.70
• /
• pp.405-416
• /
• 2005

This study contains the static buckling tests and static buckling analyses for small size grids and full size grids. The buckling tests and finite element analyses were performed to evaluate the buckling characteristics of the spacer grids in a pressurized water reactor fuel assembly and to evaluate the possibility of the prediction lot the buckling strength of spacer grids. The buckling tests were performed for small size grids and full size grids, and the correlations between buckling strength and the number of straps and the correlations between buckling strength and the number of rows are derived based on the test results. The static buckling analyses were performed to identify the effect of the number of rows and the number of columns on the buckling strength of spacer grid by a finite element method using ANSYS program and the results were compared with the buckling test results.