Elastic-plastic dynamic behavior of guard pipes due to sudden opening of longitudinal cracks in the inner pipe and crash to the guard pipe wall
Creators
- 1. Kraftwerk Union A.G., Erlangen (Germany, F.R.). Hauptbereich Reaktortechnik
Description
Integrity of guard pipes is an important parameter in the design of nuclear steam supply systems. A guard pipe shall withstand all kinds of postulated inner pipe breaks without failure. Sudden opening of a crack in the inner pipe and crash of crack borders to the guard pipe wall represent a shock problem where complex phenomena of dynamic plastification as well as dynamic behavior of the entire system have to be taken in consideration. The problem was analyzed by means of Finite Element computation using the general purpose program MARC. Equation of motion was resolved by direct integration using the Newmark β-operator. Analysis shows that after 1,2 m sec crack borders touch the guard pipe wall for the first time. At this moment a considerable amount of local plastification appears in the inner pipe wall, while the guard pipe is nearly unstressed. After initial touching, the crack borders begin to slip along the guard pipe wall. Subsequently, a short withdrawal of the crack borders and a new crash occur, while the inner pipe rolls along the guard pipe wall. The analysis procedure described is suitable for designing numerous guard pipe geometries as well as U-Bolt restraint systems which have to withstand high-energy pipe rupture impact. (orig.)
Additional details
Publishing Information
- Publisher
- North-Holland Publishing Co.
- Imprint Place
- Amsterdam, Netherlands
- ISBN
- 0444 85362 6
- Imprint Title
- Structural mechanics in reactor technology. Transactions. Vol. F
- Journal Page Range
- p. F7/4 (1-8).
Conference
- Title
- 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2).
- Dates
- 9 - 21 Aug 1979.
- Place
- Berlin, Germany, F.R.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 12588743
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; FINITE ELEMENT METHOD; M CODES; MECHANICS; PIPES; PLANNING; PRIMARY COOLANT CIRCUITS; STEAM GENERATORS
- Descriptors DEC
- BOILERS; COMPUTER CODES; COOLING SYSTEMS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; VAPOR GENERATORS
Optional Information
- Notes
- With figs.
- Secondary number(s)
- INKA-Conf--79-321-222.