Mechanical properties database of reactor pressure vessel steels related to fracture toughness evaluation

Tobita, Toru; Nishiyama, Yutaka; Onizawa, Kunio

JAEA-Data/Code 2018-013, 60 Pages, 2018/11

JAEA-Data-Code-2018-013.pdf:1.67MB

Mechanical properties of materials including fracture toughness are extremely important for evaluating the structural integrity of reactor pressure vessels (RPVs). In this report, the published data of mechanical properties of nuclear RPVs steels, including neutron irradiated materials, acquired by the Japan Atomic Energy Agency (JAEA), specifically tensile test data, Charpy impact test data, drop-weight test data, and fracture toughness test data, are summarized. There are five types of RPVs steels with different toughness levels equivalent to JIS SQV2A (ASTM A533B Class 1) containing impurities in the range corresponding to the early plant to the latest plant. In addition to the base material of RPVs, the mechanical property data of the two types of stainless overlay cladding materials used as the lining of the RPV are summarized as well. These mechanical property data are organized graphically for each material and listed in tabular form to facilitate easy utilization of data.

Investigation of research and development subjects for very high burnup fuel; Development of fuel cladding materials

Nagase, Fumihisa; Suzuki, Masahide; Furuta, Teruo; ; Hayashi, Kimio; Amano, Hidetoshi

JAERI-M 93-104, 116 Pages, 1993/05

JAERI-M-93-104.pdf:3.64MB

no abstracts in English

NSRR test on stainless steel cladding fuel rod under normal operation codition

Katanishi, Shoji; Kyoya, Masahiko; Inoue, Kimio*; ;

Nihon Genshiryoku Gakkai-Shi, 32(7), p.711 - 713, 1990/07

https://doi.org/10.3327/jaesj.32.711

no abstracts in English

Annual Progress Report on the NSRR Experiments 14

;

JAERI-M 84-046, 176 Pages, 1984/03

JAERI-M-84-046.pdf:6.85MB

no abstracts in English