Effect of postulated crack location on the pressure-temperature limit curve of reactor pressure vessel
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
In accordance with ASME Boiler and Pressure Vessel (B&PV) Code Sec.XI Appendix. G, a postulated crack is located at the beltline of a reactor pressure vessel because the neutron flux at the beltline is higher than elsewhere. This means that the distance between the core and the semi-spherical bottom head is longer than the distance between the core and the cylindrical beltline. However, several Small and Medium sized Reactors have bottom heads with diverse shapes, including dished or semi-elliptical shapes, to satisfy the requirement and performance. So, the aim of this paper is to evaluate the effect of crack location on Pressure-Temperature limit curve. To do this, two types of postulated crack location, such as beltline and semi-elliptical bottom head, were adopted to derive the Pressure-Temperature limit curve. Also, parametric studies for neutron flux, crack shape and so on were performed. As a result, core critical temperature of semi-elliptical bottom head is found to higher than that of beltline even when they have same values of thickness and neutron flux. This result will be useful to enhance the understanding of Pressure-Temperature limit curve
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 51
- Journal Issue
- 6
- Series
- 11 refs, 7 figs, 3 tabs
- Journal Page Range
- p. 1681-1688
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50066948
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACKS; DIAGRAMS; NEUTRON FLUX; PERFORMANCE; PRESSURE VESSELS; REACTOR VESSELS; SHAPE; THICKNESS
- Descriptors DEC
- CONTAINERS; DIMENSIONS; INFORMATION; RADIATION FLUX