Abstract
values from 77 energy groups were condensed to a single value by preserving overall isotope production rate from fission. Unit cell investigations were performed with a modified version of the SERPENT Monte Carlo particle transport code. The results indicate that the neutronics and radiotoxicity implications of yield energy dependence is likely to be negligible in most reactor designs.
| Original language | English |
|---|---|
| Title of host publication | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 |
| Publisher | American Nuclear Society ANS |
| Pages | 710-718 |
| Number of pages | 9 |
| ISBN (Print) | 978-0-89448-769-9 |
| Publication status | Published - Aug 2019 |
| MoE publication type | A4 Article in a conference publication |
| Event | International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering - Portland, United States Duration: 25 Aug 2019 → 29 Aug 2019 |
Conference
| Conference | International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering |
|---|---|
| Country | United States |
| City | Portland |
| Period | 25/08/19 → 29/08/19 |
Fingerprint
Keywords
- fission yield
- GEF
- RBWR
- neutronics
- radiotoxicity
Cite this
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Energy-dependent fission yields in advanced reactors. / Kunchev, Toni; Shwageraus, Eugene; Leppänen, Jaakko.
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society ANS, 2019. p. 710-718.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
TY - GEN
T1 - Energy-dependent fission yields in advanced reactors
AU - Kunchev, Toni
AU - Shwageraus, Eugene
AU - Leppänen, Jaakko
N1 - CD-ROM
PY - 2019/8
Y1 - 2019/8
N2 - Fission product yields vary over incident neutron energies and between the different fissionable nuclides. An improved representation of this energy dependence could affect the assessment of advanced reactor designs which utilise a fast neutron spectrum. The present work involves the implementation of energy-weighted averaging of fission yields in various reactor unit cell models to determine its effect on neutronics, spent fuel decay power and radiotoxicity. The energy dependence is captured through the GEF code, which has enabled the estimation of fission product yields at any incident energy point. Yieldvalues from 77 energy groups were condensed to a single value by preserving overall isotope production rate from fission. Unit cell investigations were performed with a modified version of the SERPENT Monte Carlo particle transport code. The results indicate that the neutronics and radiotoxicity implications of yield energy dependence is likely to be negligible in most reactor designs.
AB - Fission product yields vary over incident neutron energies and between the different fissionable nuclides. An improved representation of this energy dependence could affect the assessment of advanced reactor designs which utilise a fast neutron spectrum. The present work involves the implementation of energy-weighted averaging of fission yields in various reactor unit cell models to determine its effect on neutronics, spent fuel decay power and radiotoxicity. The energy dependence is captured through the GEF code, which has enabled the estimation of fission product yields at any incident energy point. Yieldvalues from 77 energy groups were condensed to a single value by preserving overall isotope production rate from fission. Unit cell investigations were performed with a modified version of the SERPENT Monte Carlo particle transport code. The results indicate that the neutronics and radiotoxicity implications of yield energy dependence is likely to be negligible in most reactor designs.
KW - fission yield
KW - GEF
KW - RBWR
KW - neutronics
KW - radiotoxicity
UR - http://www.ans.org/store/item-700432/
UR - http://www.scopus.com/inward/record.url?scp=85075364948&partnerID=8YFLogxK
M3 - Conference article in proceedings
SN - 978-0-89448-769-9
SP - 710
EP - 718
BT - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
PB - American Nuclear Society ANS
ER -