Full scale AP1000® fuel assembly mechanical test under simulated end of life (EOL) condition
Creators
- 1. Westinghouse Electric Company LLC, Hopkins, SC (United States)
Description
In order to address fuel assembly Seismic/LOCA performance with the End-of-Life (EOL) conditions, a detailed computer finite element analysis (FEA) model is needed for in-core fuel assembly impact and stress analyses. To build an accurate FEA model, a series of fuel assembly dynamic parameters need to be generated and calibrated against a set of test results which are obtained under laboratory conditions. The AP1000 EOL test fuel assembly was built by using a set of pre-conditioned grids to simulate the interaction between the fuel rod and the grid rod support features. In addition, the fuel rods were loaded into the fuel assembly skeleton with no gap between the bottom end of the rods and the top surface of the bottom nozzle. A total of six (6) tests were performed to determine the AP1000 fuel assembly static and dynamic characteristics at EOL conditions. Those tests include fuel assembly lateral vibration tests (both forced and free vibration tests), fuel assembly lateral and axial deflection tests, and fuel assembly lateral and axial dynamic impact tests. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 23th international conference on nuclear engineering (ICONE-23)
- Imprint Pagination
- [3737 p.]
- Journal Page Range
- [7 p.]
Conference
- Title
- 23. international conference on nuclear engineering
- Acronym
- ICONE-23
- Dates
- 17-21 May 2015
- Place
- Chiba (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48040497
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DAMPING; FINITE ELEMENT METHOD; FLEXIBILITY; FUEL ASSEMBLIES; FUEL RODS; HUMIDITY; LOSS OF COOLANT; MECHANICAL VIBRATIONS; NOZZLES; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR FUELING
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; MOISTURE; NUMERICAL SOLUTION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as DVD-ROM Data in PDF format. Folder Name: FullPaper; Paper ID: ICONE23-2189.pdf; 1 ref., 21 figs.