Session: CS-10-01 Recent Developments in Japanese Codes and Standards
Paper Number: 61893
Start Time: Tuesday, July 13, 2021, 05:00 PM
61893 - Evaluation of Brittle Crack Arrest Toughness for Highly-Irradiated Reactor Pressure Vessel Steels
Based on the recent revision of Japanese code, JEAC 4206-2016, which prescribes verification method of fracture toughness for in-service reactor pressure vessel (RPV) enabling to consider the crack arrest, we evaluate the crack arrest toughness for highly-irradiated RPV steel. Firstly, we confirmed the correlation between the reference temperature, TKIa, of crack arrest toughness, KIa, and the temperature corresponding to a fixed arrest load, equal to 4 kN, TFa4kN, obtained from Charpy impact test for various RPV steels, because it is difficult to obtain KIa for irradiated materials directly. To estimate the KIa for highly-irradiated RPV steels, instrumented Charpy impact tests were carried out for several A533B steels irradiated up to 1.3x1020 n/cm2 (E > 1 MeV), and TKIa for the irradiated materials were determined on the basis of the correlation between TKIa and TFa4kN. Ductile-to-brittle transition temperatures at 41 J, T41J, and its shift, ΔT41J, due to irradiation were also determined by Charpy impact tests. Comparing TKIa shift, ΔTKIa, with ΔT41J, we confirmed that ΔTKIa was relatively lower than ΔT41J for all tested materials. In JEAC 4206-2016, KIa curve can be described using the reference temperature shift for nil-ductile transition as ΔRTNDT = ΔT41J instead of ΔTKIa. The results of this study showed that the KIa curve based on ΔT41J is more conservative than KIa curve obtained using ΔTKIa.
Presenting Author: Keiko Iwata Japan Atomic Energy Agency
Authors:
Keiko Iwata Japan Atomic Energy AgencyKuniki Hata Japan Atomic Energy Agency
Tohru Tobita Japan Atomic Energy Agency
Takatoshi Hirota Mitsubishi Heavy Intustries, Ltd.
Hisashi Takamizawa Japan Atomic Energy Agency
Yasuhiro Chimi Japan Atomic Energy Agency
Yutaka Nishiyama Japan Atomic Energy Agency
Evaluation of Brittle Crack Arrest Toughness for Highly-Irradiated Reactor Pressure Vessel Steels
Category
Technical Paper Publication