Published 1979 | Version v1
Book

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

  • 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.