SCC growth behavior of SUS630 in high-temperature water. 2nd report. The effects of thermal aging, temperature and applied stress on SCC
- 1. Institute of Nuclear Safety System, Inc., Institute of Nuclear Technology, Mihama, Fukui (Japan)
Description
SUS630 (17-4 PH stainless steel) is martensitic precipitation hardened stainless steel, and its properties of high-strength and high-hardness can be controlled by the precipitation-hardening heat treatment conditions. SUS630 has been widely used for valve stems in light water reactors, because the steel had high strength and good corrosion resistance. It is known from SCC failures experience of SUS630 in field, that higher hardness materials, exposure to high-temperature and long-term use affect SCC behavior of the materials. And age hardening of materials is known to occur for long-term thermal-aging at intermediate temperature, but the influence of thermal-aging on SCC is not clear. According to the author's previous report, the SCC growth rate of SUS630 (H1100 and H1150) was increased with aging at 400degC for 3,000h. In this study, SCC growth rate measurements were performed using lower and longer aging materials which were aged at 350degC for 10,000h to evaluate the influence of thermal aging on SCC for more details. In additions, the effects of test temperature and applied stress on SCC of the materials were investigated. In unaged H1100 and H1150 (better toughness and lower hardness materials), even at a high applied stress condition (K=30 MPa m1/2), no SCC growth was observed in simulated PWR primary water at 290degC, which contained 500 ppm B, 2 ppm Li, and dissolved hydrogen (30cc STP H2/kg-H2O). On the other hand, after thermal aging at 350 and 400degC for up to 10,000h of H1100 and H1150, the SCC growth rate and the hardness increased with aging. (author)
Abstract (Japanese)
SUS630(17-4PHステンレス鋼)は,マルテンサイト系析出硬化型ステンレス鋼であり,析出硬化熱処理条件により硬度を制御することのできる高硬度で高強度の材料である.この材料は,良好な耐食性と高強度を兼ね備えていることから,軽水炉においても高強度が求められる弁棒等に用いられている.軽水炉での損傷事例では,比較的高温の使用条件で,高硬度の析出硬化熱処理条件や長期間使用後の場合にSCCが報告されている.また,長期間熱時効されると硬化が進むことが指摘されているが,そのSCC挙動への影響は解明されていない.前報ではSUS630の高温水中のSCC進展挙動に及ぼす熱時効の影響について調べ,400degCで3,000時間までの熱時効により,SCC進展が増加することを報告した.本報告では,引き続きSUS630のSCC進展挙動に及ぼす熱時効の影響について,より実使用温度に近い350degCの熱時効材を加えて評価した.併せて,試験温度と試験応力の影響について調べた.その結果,比較的高靱性のH1100とH1150は,290degC以下であれば,高応力(K=30 MPa√m)条件であってもSCC進展が観察されなかった.しかし,400degCと350degCで10,000時間までの熱時効の影響を調べた結果,H1100とH1150は熱時効時間につれて硬化し,それに伴いSCC進展速度が増加した.(著者)Additional details
Additional titles
- Original title (Japanese)
- SUS630の高温水中のSCC進展挙動.第2報.熱時効,温度,応力の影響
Publishing Information
- Journal Title
- INSS Journal
- Journal Volume
- 25
- Journal Page Range
- p. 91-101
- ISSN
- 1340-4482
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 50004655
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AGING; CHEMICAL COMPOSITION; CRACK PROPAGATION; CRACKING; DISSOLVED GASES; FRACTURE PROPERTIES; HEAT TREATMENTS; MICROSTRUCTURE; NUCLEAR POWER PLANTS; PRECIPITATION; REACTOR MATERIALS; STAINLESS STEEL-17-4PH; STRESS CORROSION; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; COPPER ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; DECOMPOSITION; FLUIDS; GASES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; MARTENSITIC STEELS; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NIOBIUM ADDITIONS; NIOBIUM ALLOYS; NUCLEAR FACILITIES; POWER PLANTS; PYROLYSIS; SEPARATION PROCESSES; SOLUTES; STAINLESS STEELS; STEEL-CR17CU4NI4NB-L; STEELS; THERMAL POWER PLANTS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 11 refs., 13 figs., 2 tabs.