Abstract
| Original language | English |
|---|---|
| Title of host publication | Proceedings of Global 2013 |
| Subtitle of host publication | Nuclear Energy at Crossroads |
| Publisher | American Nuclear Society ANS |
| Pages | 1267-1275 |
| ISBN (Print) | 978-0-89448-704-0 |
| Publication status | Published - 2013 |
| MoE publication type | Not Eligible |
| Event | Global 2013. International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads - Salt Lake City, Utah, United States Duration: 29 Sep 2013 → 3 Oct 2013 |
Conference
| Conference | Global 2013. International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads |
|---|---|
| Abbreviated title | Global 2013 |
| Country | United States |
| City | Salt Lake City, Utah |
| Period | 29/09/13 → 3/10/13 |
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Keywords
- COSI6
- nuclear energy
- closed fuel cycles
- fast reactors
- partitioning and transmutation
Cite this
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An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles. / Juutilainen, Pauli; Viitanen, Tuomas.
Proceedings of Global 2013 : Nuclear Energy at Crossroads. American Nuclear Society ANS, 2013. p. 1267-1275.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
TY - GEN
T1 - An Assessment of the Effect on Olkiluoto Repository Capacity Achievable with Advanced Fuel Cycles
AU - Juutilainen, Pauli
AU - Viitanen, Tuomas
PY - 2013
Y1 - 2013
N2 - Advanced nuclear fuel cycle scenarios were simulated with the COSI6 code, developed by CEA (France), to assess, how much the capacity of the planned nuclear waste repository at Olkiluoto (Finland) could be increased with the help of partitioning and transmutation (P&T) technologies. The repository capacity evaluation of this study is based on the comparison of the decay heats produced by the deposited waste in various scenarios. The COSI6 code is used for simulations to provide the repository decay heat curves. Applying the closed fuel cycle would change the disposal concept and schedule, because of which it is not quite straightforward to assess the impact of P&T on the capacity. However, it can be concluded that recycling the transuranic nuclides probably decreases the required volume for the disposal, but thermal dimensioning analysis is needed for more specific conclusions
AB - Advanced nuclear fuel cycle scenarios were simulated with the COSI6 code, developed by CEA (France), to assess, how much the capacity of the planned nuclear waste repository at Olkiluoto (Finland) could be increased with the help of partitioning and transmutation (P&T) technologies. The repository capacity evaluation of this study is based on the comparison of the decay heats produced by the deposited waste in various scenarios. The COSI6 code is used for simulations to provide the repository decay heat curves. Applying the closed fuel cycle would change the disposal concept and schedule, because of which it is not quite straightforward to assess the impact of P&T on the capacity. However, it can be concluded that recycling the transuranic nuclides probably decreases the required volume for the disposal, but thermal dimensioning analysis is needed for more specific conclusions
KW - COSI6
KW - nuclear energy
KW - closed fuel cycles
KW - fast reactors
KW - partitioning and transmutation
M3 - Conference article in proceedings
SN - 978-0-89448-704-0
SP - 1267
EP - 1275
BT - Proceedings of Global 2013
PB - American Nuclear Society ANS
ER -