Results 101 to 110 of about 761 (201)

DBTT measurement by use of small punch(SP) test

open access: yesDBTT measurement by use of small punch(SP) test
微小試験片による延性脆性遷移温度(DBTT)の評価法について、スモールパンチ(SP)試験を中心に検討を行った。熱時効、冷間加工、中性子照射を行った21/4Cr-1Mo鋼及び鉄基モデル合金を用い、SP試験によるDBTT評価の課題を検討した結果、SPによるDBTTとシャルピー試験によるDBTTは全般的には良い相関が得られた。しかしながら、粒界脆化型のDBTTの上昇に関しては、SP試験片の破壊破面観察等を組み合わせることにより、脆化のより的確な判断を行っていく必要があることが判った。
openaire  

Ductility in bending of molybdenum alloys irradiated between 425 and 1000/sup 0/C

open access: yes, 1979
Molybdenum and the alloys Mo--0.5% Ti and TZM were irradiated at four temperatures between 425 and 1000/sup 0/C, to a displacement level of 11 dpa at a fluence of 2.5 x 10/sup 26/ n m /sup -2/ (> 0.1 MeV).
Cox, B.L., Wiffen, F.W.
core  

Effect of Specimen Geometry on Charpy Impact Test Results for Ferritic Steel Irradiated in JMTR

open access: yes, 2010
application/pdfIn order to develop the small-scale specimen technology in Charpy impact testing for ferritic steels, the effects of specimen size and notch geometry on the upper shelf energy (USE) and ductile-to-brittle transition temperature (DBTT) were
KURISHITA, Hiroaki   +3 more
core   +2 more sources

Radiation damage in tungsten under high-energy He-ion irradiation

open access: yesCommunications Materials
Tungsten (W) is a primary candidate for plasma-facing components (PFCs) in fusion reactors and hybrid fission-fusion reactors. However, W suffers from severe microstructural damage under Helium (He) ion irradiation in operation conditions.
Yinghang Liu   +10 more
doaj   +1 more source

Strength, ductility, and ductile-brittle transition temperature for MFR (magnetic fusion reactor) candidate vanadium alloys

open access: yes, 1987
The dependence of the yield strength, tensile strength, elongation, and reduction in area on temperature for the V-15Ti-7.5Cr, V-20Ti, V-15Cr-5Ti, V-12Cr-5Ti, V-10Cr-5Ti, and V-3Ti-1Si alloys was determined from tensile tests at temperatures ranging from
Lee, R. H.   +3 more
core  

DESTRUCTIVE AND NON-DESTRUCTIVE TECHNIQUES APPLIED TO THE CHARACTERIZATION OF AS-CAST MODEL STEELS WITH PARAMETRIC VARIATION OF Ni, Mn, Si AND Cr CONTENT

open access: yes, 2007
The present work is aimed to investigate the role and influence of certain elements as Cr, Ni, Mn and Si on the radiation stability of reactor pressure vessel steels.
DEGMOVA Jarmila, DEBARBERIS Luigi
core  

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