Evaluation of WWER-1000 vessel materials fracture toughness
The lifetime of WWER-1000-type reactor vessels is finally conditioned by the fracture toughness (crack growth resistance) of RPV materials. Up to now in line with the regulations the fracture toughness is characterized by the critical temperature of brittleness determined by the results of the Cha...
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| Format: | Article |
| Language: | English |
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Institute for Nuclear Research, National Academy of Sciences of Ukraine
2007-03-01
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| Series: | Ядерна фізика та енергетика |
| Online Access: | http://jnpae.kinr.kiev.ua/19(1)/Articles_PDF/jnpae-2007-1(19)-0083-Grynik.pdf |
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| author | E. U. Grynik V. N. Revka L. I. Chyrko Yu. V. Chaikovsky |
| author_facet | E. U. Grynik V. N. Revka L. I. Chyrko Yu. V. Chaikovsky |
| author_sort | E. U. Grynik |
| collection | DOAJ |
| description | The lifetime of WWER-1000-type reactor vessels is finally conditioned by the fracture toughness (crack growth
resistance) of RPV materials. Up to now in line with the regulations the fracture toughness is characterized by the critical
temperature of brittleness determined by the results of the Charpy specimen impact testing. Such approach is typical
for all countries operating the water pressure reactors. However, regulatory approach is known from the western specialists
not always to characterize adequately the crack growth resistance of the vessel materials and in some cases to
underestimate their characteristics in the reference state that leads to unreasonably high conservatism. Excessive conservatism
may lead to the invalid restrictions in the operating modes and the service life of the reactor vessel. Therefore
there appeared the necessity to apply another approaches based on the state-of-the-art experimental methods of the
fracture mechanics and allowing evaluating the fracture toughness parameters sufficiently. The paper presents the results
of the comparison of the regulatory approach and the Master curve approach from the point of view of the adequate
determination of the vessel material crack growth resistance parameters. Analysis of the experimental data of the
surveillance specimens illustrated the potential possibility of applying the new statistical method for the WWER-1000-
type reactor vessel lifetime extension. |
| format | Article |
| id | doaj-art-741341d0cd094caebb4a825b55e8b7e4 |
| institution | DOAJ |
| issn | 1818-331X 2074-0565 |
| language | English |
| publishDate | 2007-03-01 |
| publisher | Institute for Nuclear Research, National Academy of Sciences of Ukraine |
| record_format | Article |
| series | Ядерна фізика та енергетика |
| spelling | doaj-art-741341d0cd094caebb4a825b55e8b7e42025-08-20T03:19:08ZengInstitute for Nuclear Research, National Academy of Sciences of UkraineЯдерна фізика та енергетика1818-331X2074-05652007-03-0181(19)8388Evaluation of WWER-1000 vessel materials fracture toughnessE. U. Grynik0V. N. Revka1L. I. Chyrko2Yu. V. Chaikovsky3Institute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineInstitute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineInstitute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineInstitute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineThe lifetime of WWER-1000-type reactor vessels is finally conditioned by the fracture toughness (crack growth resistance) of RPV materials. Up to now in line with the regulations the fracture toughness is characterized by the critical temperature of brittleness determined by the results of the Charpy specimen impact testing. Such approach is typical for all countries operating the water pressure reactors. However, regulatory approach is known from the western specialists not always to characterize adequately the crack growth resistance of the vessel materials and in some cases to underestimate their characteristics in the reference state that leads to unreasonably high conservatism. Excessive conservatism may lead to the invalid restrictions in the operating modes and the service life of the reactor vessel. Therefore there appeared the necessity to apply another approaches based on the state-of-the-art experimental methods of the fracture mechanics and allowing evaluating the fracture toughness parameters sufficiently. The paper presents the results of the comparison of the regulatory approach and the Master curve approach from the point of view of the adequate determination of the vessel material crack growth resistance parameters. Analysis of the experimental data of the surveillance specimens illustrated the potential possibility of applying the new statistical method for the WWER-1000- type reactor vessel lifetime extension.http://jnpae.kinr.kiev.ua/19(1)/Articles_PDF/jnpae-2007-1(19)-0083-Grynik.pdf |
| spellingShingle | E. U. Grynik V. N. Revka L. I. Chyrko Yu. V. Chaikovsky Evaluation of WWER-1000 vessel materials fracture toughness Ядерна фізика та енергетика |
| title | Evaluation of WWER-1000 vessel materials fracture toughness |
| title_full | Evaluation of WWER-1000 vessel materials fracture toughness |
| title_fullStr | Evaluation of WWER-1000 vessel materials fracture toughness |
| title_full_unstemmed | Evaluation of WWER-1000 vessel materials fracture toughness |
| title_short | Evaluation of WWER-1000 vessel materials fracture toughness |
| title_sort | evaluation of wwer 1000 vessel materials fracture toughness |
| url | http://jnpae.kinr.kiev.ua/19(1)/Articles_PDF/jnpae-2007-1(19)-0083-Grynik.pdf |
| work_keys_str_mv | AT eugrynik evaluationofwwer1000vesselmaterialsfracturetoughness AT vnrevka evaluationofwwer1000vesselmaterialsfracturetoughness AT lichyrko evaluationofwwer1000vesselmaterialsfracturetoughness AT yuvchaikovsky evaluationofwwer1000vesselmaterialsfracturetoughness |