Evaluation of seismic integrity for an integral reactor assembly
- 1. Korea Power Engineering Company (Korea, Republic of)
- 2. Korea Institute of Nuclear Safety (Korea, Republic of)
Description
The structural integrity of integral reactor assembly of 65 MWt thermal capacity is assessed by using the commercial finite element package ANSYS in order to evaluate the seismic safety margin. First of all, the modal analyses are performed using the various analysis models with/without the fluid coupling effect in order to validate a super element model and to evaluate the coupling effect on natural frequency. Based on the modal analysis results, the seismic analyses are performed using the ground response spectrum defined in Reg. Guide 1.60. Finally, time-history analyses are performed using the modal analysis results, the super element model and an inertia load approach. As a result, the reliable and efficient seismic analysis model for an integral reactor assembly is developed and it is found that an integral reactor assembly has the sufficient seismic safety margin. The results show that the resonance of the integral reactor can hardly occurred because its fundamental frequency (70 - 72 Hz) is relatively higher than zero period acceleration frequency (33 Hz). Therefore, there is less possibility of reactor damage from earthquake than other structures
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers - ASME
- Imprint Place
- New York (United States)
- ISBN
- 0-7918-4688-1
- Imprint Title
- Proceedings of the 12. international conference on nuclear engineering. Volume 2
- Imprint Pagination
- 864 p.
- Journal Page Range
- p. 361-365
Conference
- Title
- 12. international conference on nuclear engineering - ICONE 12
- Dates
- 25-29 Apr 2004
- Place
- Arlington - Virginia (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 38060085
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; COMPUTERIZED SIMULATION; FINITE ELEMENT METHOD; PACKAGE REACTORS; PRESSURE VESSELS; RESPONSE FUNCTIONS; RISK ASSESSMENT; SAFETY MARGINS; SEISMICITY; SPECTRAL RESPONSE
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; CONTAINERS; FUNCTIONS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; SIMULATION; TRANSPORTABLE REACTORS
Optional Information
- Notes
- 9 refs.