Simplified P-T limit curve generator for reactor pressure vessels
Creators
- 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.htmlAdditional 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
Identifiers
Publishing Information
- Imprint Pagination
- 22 p.
- Report number
- CRIEPI--Q17006
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49097385
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CHEMICAL COMPOSITION; COMPUTERIZED SIMULATION; COOLANTS; FRACTURE PROPERTIES; IRRADIATION; NEUTRON FLUX; NUSSELT NUMBER; POISSON RATIO; PWR TYPE REACTORS; REACTOR CORES; REACTOR VESSELS; STRESS INTENSITY FACTORS; TEMPERATURE DISTRIBUTION; THERMAL CONDUCTIVITY; YOUNG MODULUS
- Descriptors DEC
- CONTAINERS; DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; PHYSICAL PROPERTIES; POWER REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs., 11 figs., 2 tabs.