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JAEA Reports

Evaluation of charpy impact property in high strength ferritic/martensitic steel (PNC-FMS)

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JNC TN9400 2000-035, 164 Pages, 2000/03

JNC-TN9400-2000-035.pdf:3.67MB

High Strength Ferritic/Martensitic Steel (PNC-FMS : 0.12C-11Cr-0,5Mo-2W-0.2V-0.05Nb), developed by JNC, is one of the candidate materials for the long-life core of large-scale fast breeder reactor. Ductile brittle transition temperature (DBTT) was tentatively determined in 1992 in material design base standard of PNC-FMS. Howevcr, specimen size effect on impact property and upper shelf energy (USE) have not been evaluated. ln this study, effects of specimen size, thermal aging and neutron irradiation on the charpy impact property of PNC-FMS were evaluated, using together with recently obtained data. The design value of USE and DBTT as fabricated and each correlation of aging and irradiation effects were determined. The results are summarized as follows. (1)lt was found that USE is related to (Bb) as USE=m(Bb)$$^{n}$$, where B is specimen width, b is ligament size and both m and n are constant. For PNC-FMS, n value is equal to 1.4. It's possible to determine n value from USE (J) for full size specimen using the correlation: n=1.38$$times$$10$$^{-3}$$ USE + 1.20. (2)lt was clarified that DBTT is correlated with (BKt) as DBTT=p(log$$_{10}$$BKt)+q, where Kt is elastic stress concentration factor and both p and q are constant. For PNC-FMS, the correlation is as follows: DBTT=119(log$$_{10}$$BKt)-160. (3)DBTT estimated at the irradiation temperature from 350 to 650 $$^{circ}$$C for sub size specimen (width and height are 3 and 10 mm, respectively), was below 180 $$^{circ}$$C, based on the design value of DBTT as fabricated and each correlation of aging and irradiation effects.

Oral presentation

Changes in strength of PNC-FMS for wrapper tube of fast reactor by long-term thermal aging

Fujita, Koji; Shizukawa, Yuta; Tanno, Takashi; Yano, Yasuhide

no journal, , 

Japan Atomic Energy Agency has been developed 11 Cr martensitic steel PNC-FMS as the candidate material for wrapper tubes of fast reactors. Developing database of property changes by thermally aging is necessary to clarify the irradiation effects from post irradiation experimental data. Tensile tests and hardness measurement of PNC-FMS aged up to 45,000 hours were carried out. Tensile test and hardness test after the thermal aging showed that the strength of specimens aged at 600$$^{circ}$$C or higher decreased with aging time. It was shown that the decrease trend was described by linear correlation with Larson-Miller parameter. This means that the strength decrease should have been made by microstructural degradation due to the diffusion-controlled process.

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