Stress analyses for reactor pressure vessels by the example of a product line '69 boiling water reactor
Creators
- 1. TUEV SUED Energietechnik GmbH, Mannheim (Germany). Abt. Strukturverhalten
- 2. TUEV SUED Industrie Service GmbH, Muenchen (Germany). Abt. Behaelter und Turbosatz
- 3. TUEV NORD SysTec GmbH und Co. KG, Hamburg (Germany). Abt. Festigkeit und Konstruktion
Description
The reactor pressure vessels (RPV) of boiling water reactors (BWR) belonging to the product line '69 have unusually designed heads. The spherical cap-shaped bottom head of the vessel is welded directly to the support flange of the lower shell course. This unusual construction has led repeatedly to controversial discussions concerning the limits and admissibility of stress intensities arising in the junction of the bottom head to the cylindrical shell. In the present paper, stress analyses for the design conditions are performed with the finite element method in order to determine and categorize the occurring stresses. The procedure of stress classification in accordance with the guidelines of German KTA 3201.2 and Section III of the ASME Code (Subsection NB) is described and subsequently demonstrated by the example of a typical BWR vessel. The accomplished investigations yield allowable stress intensities in the considered area. Additionally, limit load analyses are carried out to verify the obtained results. Complementary studies, performed for a torispherical head, prove that the determined maximum peak stresses in the junction between the bottom head and the cylindrical shell are not unusual also for pressure vessels with regular bottom head constructions. (orig.)
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 76
- Journal Issue
- 4
- Journal Page Range
- p. 225-230
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 43000071
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; BWR TYPE REACTORS; CYLINDRICAL CONFIGURATION; FINITE ELEMENT METHOD; FLANGES; PRESSURE VESSELS; SHELLS; SPHERICAL CONFIGURATION; STRESS ANALYSIS; STRESSES; SUPPORTS; WELDED JOINTS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; CONFIGURATION; CONTAINERS; ENRICHED URANIUM REACTORS; JOINTS; MATHEMATICAL SOLUTIONS; MECHANICAL STRUCTURES; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS