Composite containment for nuclear power
Description
This paper deals with a new concept in which a steel liner is employed which carries much of the primary membrane loads. This type of structure is similar in some aspects to the previously described system: a mat, lined with a thin plate on its top surface, is similar to concrete containment; a cylinder and hemispherical dome, made up of steel plate and concrete, is is about 2.5 feet thick (the minimum required for radiation shielding). The governing equations have been derived accounting for the fact that the stresses in the steel liner are calculated in accordance with the shell equations for hoop and meridional strains and temperature and the fact that the reinforcing bars respond as linear members. Because of composite behavior hoop and meridional membrane strain compatibility is maintained between the steel liner and the reinforcing bars. Similarly the equations for calculating the discontinuity moments and shears in the liner have been derived considering the fact that the reinforcing bars participate with the steel liner in structural response. The response of composite containment to DBA is one in which the proportion of membrane forces carried in the steel liner and the reinforced concrete vary depending upon the internal pressure and temperature. When peak pressure is reached and liner temperature is relatively low, the membrane forces are carried by the steel plate and the reinforcing bars roughly in proportion to the projected areas. On the other hand, when the peak liner temperature is reached the liner will be much hotter than the re-bar. Based upon the elastic and thermal properties the difference in membrane stress between the steel liner and the reinforcing bars will be such that the portion of membrane load carried by the reinforci
Availability note (English)
MF available from INIS under the Report Number.Additional details
Additional titles
- Augmented title (English)
- LWR, LMFBR, HTGR and HWR
Publishing Information
- Imprint Pagination
- J 1/5, 12 p.
- Report number
- INIS-mf--4373
Conference
- Title
- 4. International conference on structural mechanics in reactor technology.
- Dates
- 15 - 19 Aug 1977.
- Place
- San Francisco, Calif., USA.
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 9395781
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SHELLS; DESIGN BASIS ACCIDENTS; HTGR TYPE REACTORS; LMFBR TYPE REACTORS; NUCLEAR POWER PLANTS; PRESSURE VESSELS; PRESTRESSED CONCRETE; PWR TYPE REACTORS; SPECIFICATIONS; STEELS; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; ALLOYS; BREEDER REACTORS; BUILDING MATERIALS; CARBON ADDITIONS; CONCRETES; CONTAINERS; CONTAINMENT; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTORS; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS