Published September 2019 | Version v1
Journal article

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