Evaluation of plane strain fracture toughness of neutron-irradiated A533B steels in nuclear reactor vessel surveillance test
Description
In structural integrity assessment for nuclear reactor technology, one of the most important subject is to develop an estimation procedure of the cleavage controlled fracture toughness KIC from standard Charpy V surveillance test data for neutron-irradiated pressure vessel steels. This paper proposes an empirical representation of KIC fracture toughness transition curve for both unirradiated and irradiated A533B steels. The fitting curves derived are written in forms such as, KIC(Cv))=138(Cv-us)/Cv-1)-0.45+25(MNm-3/2), KIC(Cv) <= 165MNm-3/2, KId(Cv)=44.7(Cv-us)/Cv-1)-0.33+20(MNm-3/2), KId(Cv) <= 108MNm-3/2, where KIC(Cv) and KId(Cv) mean the plane strain fracture toughness parameters characterizing an onset of the cleavage instability under static and dynamic loading conditions respectively, Cv is a value of standard Charpy V absorbed energy at a test temperature concerned and Cv-us is a upper shelf energy for the unirradiated steel. It is here demonstrated that the estimated values of KIC(Cv) and KId(Cv) show a good agreement with valid KIC and KId determined experimentally for both unirradiated and irradiated steels. (author)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.24.68Abstract (Japanese)
小型で簡便な試験法である標準シャルピー試験データから破壊靱性を求めることができるようにすることは重要であり急務の課題といえる。最近、Oldfieldは多くの破壊靱性データ(KIC、KId、JICなど)を基に破壊靱性の下限値を関数tanhを含む式により表示し、熱処理の異なる材料も含めて統計学的に処理できることを示した。また、WullaertらはOldfieldと同じ表示式で照射材の破壊靱性を含めて破壊靱性曲線が得られることを報告した。しかしながら、これらの結果は単に統計学的なデータ処理により数式処理したもので、シャルピー試験データから破壊靱性値を求める具体的な方法は示していない。本報は中性子照射監視試験で得られるシャルピー吸収エネルギーCvより、へき開型破壊靱性KIC(およびKId)を求める方法を確立することを目的としている。ここでは、数種類の異なるA533B鋼について非照射材のKIC (およびKId) とCvデータの相関式に基づく照射材のKIC (およびKId) の推定法について述べる。 (日本)Additional details
Additional titles
- Original title (Japanese)
- 原子炉圧力容器監視試験における中性子照射材のへき開平面ひずみ破壊靱性評価
Identifiers
- DOI
- 10.3327/jaesj.24.68;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 24
- Journal Issue
- 1
- Journal Page Range
- p. 68-77
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53116602
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CHARPY TEST; CLEAVAGE; EVALUATION; EXPERIMENTAL DATA; FRACTURE PROPERTIES; INSPECTION; NEUTRON BEAMS; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; REACTOR SAFETY; STEEL-ASTM-A533-B; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ALLOYS; BEAMS; CARBON ADDITIONS; CARBON STEELS; CONTAINERS; DATA; DESTRUCTIVE TESTING; IMPACT TESTS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; LOW ALLOY STEELS; MANGANESE ALLOYS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MICROSTRUCTURE; MOLYBDENUM ADDITIONS; MOLYBDENUM ALLOYS; NICKEL ADDITIONS; NICKEL ALLOYS; NUCLEON BEAMS; NUMERICAL DATA; PARTICLE BEAMS; RADIATION EFFECTS; SAFETY; STEEL-MNNIMO; STEELS; TESTING; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 2999600; This record replaces 14776805