Evaluation of seismic qualification requirements for in-line components (active valves) following the seismic design load change
Description
Most valves installed in Optimized Power Reactor 1000 (OPR1000) have been qualified using the required response spectra or zero period acceleration (ZPA) having maximum 5.0g for safety shutdown earthquake (SSE) loads. The ground acceleration for the SEE loads in Advanced Power Reactor 1400 (APR1400) has increased to 0.3g from 0.2g which has been applied to OPR1000. This increase would result in higher response acceleration in piping system as well as in-line components such as active valves. If pipe and equipment interface requirements are checked during the design stage, the equipment allowable rather than the pipe stress allowable seems to be exceeded. In order to reduce the interface loads to an acceptable level, many supports need to be added to the piping systems. It became a sensitive issue to set the appropriate acceleration value for the active valve qualification to a reasonable level since an increase in the seismic loads may cause an extra expenditure to the equipment suppliers in qualifying these components. Furthermore, in the process of compromising between piping stresses and pipe/equipment interface loads, it is a challenge to keep a good balance between adding supports and not losing flexibility of the piping system. Because of these concerns, various kinds of case studies have been performed to evaluate the effect of the increased seismic design loads associated with the qualification of in-line components (valves) of the APR1400. As a result of analyzing more than 430 cases studies, the maximum seismic response accelerations are ranged from 5.0g to 5.7g. In this regard, 6g acceleration value could be regarded as an appropriate acceleration value for the equipment qualification considering 20% margin to take account for possible deviation from the design condition that could happen during the construction stage. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [7 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39040995
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATION; EARTHQUAKES; EQUIPMENT INTERFACES; GROUND MOTION; NUCLEAR POWER PLANTS; PIPELINES; POWER REACTORS; REACTOR SHUTDOWN; SEISMIC EFFECTS; SUPPORTS; VALVES
- Descriptors DEC
- CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; MECHANICAL STRUCTURES; MOTION; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; SEISMIC EVENTS; SHUTDOWN; THERMAL POWER PLANTS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name Final Paper, Paper ID ICONE15-10086.pdf; 5 refs., 2 figs., 8 tabs.