Abstract
| Original language | English |
|---|---|
| Title of host publication | Baltica VIII |
| Subtitle of host publication | Life Management and Maintenance for Power Plants |
| Place of Publication | Espoo |
| Publisher | VTT Technical Research Centre of Finland |
| Pages | 256-270 |
| Volume | 1 |
| ISBN (Electronic) | 978-951-38-7592-3 |
| ISBN (Print) | 978-951-38-7591-6 |
| Publication status | Published - 2010 |
| MoE publication type | B3 Non-refereed article in conference proceedings |
| Event | BALTICA VIII - International Conference on Life Management and Maintenance for Power Plants - Helsinki-Stockholm, Finland Duration: 18 May 2010 → 20 May 2010 |
Publication series
| Name | VTT Symposium |
|---|---|
| Publisher | VTT |
| Number | 264 |
| ISSN (Print) | 0357–9387 |
| ISSN (Electronic) | 1455–0873 |
Conference
| Conference | BALTICA VIII - International Conference on Life Management and Maintenance for Power Plants |
|---|---|
| Country | Finland |
| City | Helsinki-Stockholm |
| Period | 18/05/10 → 20/05/10 |
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Creep in generation IV nuclear applications. / Rissanen, Laura.
Baltica VIII: Life Management and Maintenance for Power Plants. Vol. 1 Espoo : VTT Technical Research Centre of Finland, 2010. p. 256-270 (VTT Symposium; No. 264).Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific
TY - GEN
T1 - Creep in generation IV nuclear applications
AU - Rissanen, Laura
PY - 2010
Y1 - 2010
N2 - Nuclear power has an important role in fulfilling the world's growing energy needs and reducing the carbon dioxide emission. Six new, innovative nuclear energy systems have been identified and selected for further development by the international Generation Four International Forum (GIF). These generation four (Gen IV) nuclear energy systems include a variety of reactor, energy conversion and fuel cycle technologies. The successful development and deployment of these largely depend on the performance and reliability of the available structural materials. These potential materials need to sustain their mechanical properties up to high temperatures, high neutron doses and corrosive environments of the new or enhanced types of coolants. Current knowledge on material properties, material-coolant interaction and especially material degradation processes in these new environments are limited. This paper gives an overview of the Gen IV material issues with special emphasis on European design of supercritical light water reactor concept high performance light water reactor (HPLWR). The challenges for the structural materials and the components most likely to suffer from creep and creep-irradiation are highlighted. Some results from relatively short term creep testing in supercritical water are presented for AISI 316NG, 347H and 1.4970 steels. The 1.4970 steel was superior in creep and oxidation resistance.
AB - Nuclear power has an important role in fulfilling the world's growing energy needs and reducing the carbon dioxide emission. Six new, innovative nuclear energy systems have been identified and selected for further development by the international Generation Four International Forum (GIF). These generation four (Gen IV) nuclear energy systems include a variety of reactor, energy conversion and fuel cycle technologies. The successful development and deployment of these largely depend on the performance and reliability of the available structural materials. These potential materials need to sustain their mechanical properties up to high temperatures, high neutron doses and corrosive environments of the new or enhanced types of coolants. Current knowledge on material properties, material-coolant interaction and especially material degradation processes in these new environments are limited. This paper gives an overview of the Gen IV material issues with special emphasis on European design of supercritical light water reactor concept high performance light water reactor (HPLWR). The challenges for the structural materials and the components most likely to suffer from creep and creep-irradiation are highlighted. Some results from relatively short term creep testing in supercritical water are presented for AISI 316NG, 347H and 1.4970 steels. The 1.4970 steel was superior in creep and oxidation resistance.
M3 - Conference article in proceedings
SN - 978-951-38-7591-6
VL - 1
T3 - VTT Symposium
SP - 256
EP - 270
BT - Baltica VIII
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -