Influence of gaps on seismic behaviour of the primary system of a PWR
Creators
- 1. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Paris La Defense (France)
Description
This paper deals with the influence of gaps on the dynamic behaviour of the Reactor Coolant System (RCS) of the french PWR when subjected to an earthquake event. One of the basic rule of the french RCS design is that primary components and coolant pipes should not be constrained during the thermal motions of the RCS and of Civil Works. This purpose can be ensured by using, for the RCS lateral support, snubbers which can accomodate without constraints any slow motion. But this solution is not always possible due to mechanical limits, space constraints, or even costs. An other solution, which is used in the french plants for the lateral support of the steam generators, is to use stops with adequate gaps. These gaps, which are adjusted with shims during the hot functional testing, change during lifetime, particularly because of temperature transients. In a first step, the paper gives insight on the reality of these geometrical gaps; the measures of the size of the gaps on site are in good agreement with calculation results. In a second step the paper shows the mechanical analysis process, taking into account the gaps, using a seismic non linear time history analysis of a RCS-building coupled model subjected to base motions (translations and rotations); the time history analysis uses a very performant modal superposition method in a relative coordinated system. (orig./RW)
Additional details
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam (Netherlands)
- ISBN
- 0 444 86695 7
- Imprint Title
- Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. F
- Imprint Pagination
- 426 p.
- Journal Page Range
- p. 169-177.
Conference
- Title
- 7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7).
- Dates
- 22-26 Aug 1983.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 15050026
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DYNAMIC LOADS; EARTHQUAKES; IMPACT SHOCK; MECHANICAL VIBRATIONS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; SEISMIC EFFECTS
- Descriptors DEC
- COOLING SYSTEMS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EUR--8596 DE/EN/FR.