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Onizawa, Kunio
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1
Investigation on the evaluation of cleavage fracture toughness using PCCv specimens in the ductile-brittle transition range of reactor pressure vessel steels Kunio Onizawa, Tohru T...
by
Onizawa
,
Kunio
Published 1997
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JAERI's contribution to the IAEA coordinated research programme on "Assuring structural integrity of reactor pressure vessels" (CRP-IV) : final report (contract research) Kunio Oza...
by
Onizawa
,
Kunio
Published 2000
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3
JAERI contribution for the IAEA coordinated research program phase III (CRP - 3) on : "optimizing of reactor pressure vessel surveillance programmes and their analysis" Kunio Oniza...
by
Onizawa
,
Kunio
Published 1993
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4
Irradiation experiments of low copper A533B steels for reactor pressure vessel tested in JMTR Masahide Suzuki, Kunio Onizawa, Minoru Kizaki.
by
Suzuki, Masahide
Published 1994
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Related Subjects
Brittle Fracture
Chemical composition
Fracture Toughness
Integrity
Irradiation
Irradiation Embrittlement
Reactor pressure vessel
Statistical Analysis
Transition Temperature
embrittlement
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