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KNOVEL_ocn794597465 |
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OCoLC |
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20231027140348.0 |
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120601s2009 au a ob i000 0 eng d |
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|a MYG
|b eng
|c MYG
|d OCLCQ
|d OCLCF
|d OCLCA
|d OCLCO
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|a 9789201110091
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|a 920111009X
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|a (OCoLC)794597465
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|a TK9211.5
|b .M37 2009
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|a 621.48332
|b M393
|2 22
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|a UAMI
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|a Master curve approach to monitor fracture toughness of reactor pressure vessels in nuclear power plants.
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|a Vienna, Austria :
|b International Atomic Energy Agency,
|c 2009.
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|a 1 online resource (167 pages) :
|b illustrations (chiefly color).
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|a text
|b txt
|2 rdacontent
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|a computer
|b c
|2 rdamedia
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|a online resource
|b cr
|2 rdacarrier
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|a IAEA-TECDOC,
|x 1011-4289 ;
|v 1631
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|a "October 2009."
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|a "The IAEA officers responsible for this publication were K.S. Kang and L. Kupca of the Division of Nuclear Power"--PDF Foreword page.
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|a Includes bibliographical references.
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|a Print version record.
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|a System requirements: Adobe Acrobat Reader for Windows.
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|a This publication provides information about the master curve approach for assessing the structural integrity of reactor pressure vessels (RPVs) under current and future operation and accident conditions in nuclear power plants (NPPs). This direct measurement of fracture toughness approach is technically superior to the correlative and indirect methods used in the past to assess irradiated RPV integrity. The results in the report should allow utility engineers and scientists to directly measure fracture toughness using small surveillance sized specimens and apply the results using the master curve approach for RPV structural integrity assessment in NPPs.--Publisher's description.
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|a Background -- Topic areas -- Specimen size, geometry, and constraint -- Loading rate effects and qualification of impact fracture toughness testing -- Master curve shape -- Conclusions and recommendations.
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|a Knovel
|b ACADEMIC - Mechanics & Mechanical Engineering
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|a Knovel
|b ACADEMIC - Electrical & Power Engineering
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|a Nuclear pressure vessels
|x Materials
|x Effect of radiation on.
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|a Nuclear pressure vessels
|x Materials
|x Fracture.
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|a Nuclear pressure vessels
|x Materials
|x Embrittlement.
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650 |
|
0 |
|a Nuclear pressure vessels
|x Materials
|x Testing.
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|
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|a Nuclear power plants
|x Materials
|x Effect of radiation on.
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|a Réacteurs nucléaires
|x Caissons
|x Matériaux
|x Effets du rayonnement sur.
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650 |
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|a Réacteurs nucléaires
|x Caissons
|x Matériaux
|x Rupture.
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6 |
|a Réacteurs nucléaires
|x Caissons
|x Matériaux
|x Fragilisation.
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650 |
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|a Centrales nucléaires
|x Matériaux
|x Effets du rayonnement sur.
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650 |
|
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|a Nuclear power plants
|x Materials
|x Effect of radiation on.
|2 fast
|0 (OCoLC)fst01040599
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650 |
|
7 |
|a Nuclear pressure vessels
|x Materials
|x Effect of radiation on.
|2 fast
|0 (OCoLC)fst01040694
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650 |
|
7 |
|a Nuclear pressure vessels
|x Materials
|x Testing.
|2 fast
|0 (OCoLC)fst01040696
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700 |
1 |
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|a Kang, K. S.
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1 |
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|a Kupca, L.
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2 |
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|a International Atomic Energy Agency.
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776 |
0 |
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|i Print version:
|t Master curve approach to monitor fracture toughness of reactor pressure vessels in nuclear power plants.
|d Vienna, Austria : International Atomic Energy Agency, 2002
|w (OCoLC)526091351
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830 |
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0 |
|a IAEA-TECDOC ;
|v 1631.
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856 |
4 |
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|u https://appknovel.uam.elogim.com/kn/resources/kpMCAMFTRA/toc
|z Texto completo
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994 |
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|a 92
|b IZTAP
|