Published March 2018 | Version v1
Report

Simplified P-T limit curve generator for reactor pressure vessels

  • 1. Central Research Institute of Electric Power Industry, Materials Science Research Laboratory, Yokosuka, Kanagawa (Japan)

Description

Although the fracture toughness of reactor pressure vessels decreases over time due to neutron irradiation, the integrity of the vessel must be retained during plant operation under fracture toughness degradation. JEAC 4206-2007 specifies validation test methods for the fracture toughness with the pressure-temperature limit curve (P-T curve) which is one of the standard for the vessel integrity. The P-T curve is obtained by comparing the fracture toughness of the vessel and the stress intensity factors obtained from hoop and thermal stresses. We have developed a numerical analysis program to facilitate the P-T curve evaluation, which includes the thermal conductivity in the vessel wall and P-T curve generation based on JEAC 4206-2007. The numerical simulation of thermal conductivity is carried out using the axial symmetric one-dimensional thermal conductivity equation and the program allows the sensitivity of parameters such as RTNDT, chemical components and vessel dimensions to be analyzed. Our program has been applied to evaluate the curve for long term operation as an example to showcase its potential. (author)

Availability note (English)

Available from https://criepi.denken.or.jp/jp/kenkikaku/report/detail/Q17006.html

Additional details

Additional titles

Original title (Japanese)
原子炉圧力容器の圧力・温度制限曲線簡易作成プログラムの開発

Publishing Information

Imprint Pagination
22 p.
Report number
CRIEPI--Q17006

Optional Information

Notes
9 refs., 11 figs., 2 tabs.