Abstract
| Original language | English |
|---|---|
| Title of host publication | Proceedings |
| Subtitle of host publication | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 |
| Pages | 926-937 |
| Publication status | Published - 2013 |
| MoE publication type | Not Eligible |
| Event | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 - Sun Valley, ID, United States Duration: 5 May 2013 → 9 May 2013 |
Publication series
| Name | |
|---|---|
| Publisher | Idaho National Laboratory |
| Volume | 2 |
Conference
| Conference | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 |
|---|---|
| Abbreviated title | M&C 2013 |
| Country | United States |
| City | Sun Valley, ID |
| Period | 5/05/13 → 9/05/13 |
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Keywords
- coupled calculation
- material properties
- Monte Carlo
- multi-physics
Cite this
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Internal neutronics-temperature coupling in serpent 2 : Reactivity differences resulting from choice of material property correlations. / Valtavirta, Ville.
Proceedings: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013. 2013. p. 926-937.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
TY - GEN
T1 - Internal neutronics-temperature coupling in serpent 2
T2 - Reactivity differences resulting from choice of material property correlations
AU - Valtavirta, Ville
PY - 2013
Y1 - 2013
N2 - This paper describes the unique way of simultaneously solving the power and temperature distributions of a nuclear system with the Monte Carlo neutron transport code Serpent 2. The coupled solution is achieved through the implementation of an internal temperature solver and material property correlations in the code. The program structure is reviewed concerning the temperature solver and the internal correlations as well as the internal coupling between these two and the neutron transport part. To estimate the reactivity differences resulting from correlation choices a simple pin-cell case has been calculated. It is established, that some correlation choices may result in difference in reactivity of approximately 100 pcm.
AB - This paper describes the unique way of simultaneously solving the power and temperature distributions of a nuclear system with the Monte Carlo neutron transport code Serpent 2. The coupled solution is achieved through the implementation of an internal temperature solver and material property correlations in the code. The program structure is reviewed concerning the temperature solver and the internal correlations as well as the internal coupling between these two and the neutron transport part. To estimate the reactivity differences resulting from correlation choices a simple pin-cell case has been calculated. It is established, that some correlation choices may result in difference in reactivity of approximately 100 pcm.
KW - coupled calculation
KW - material properties
KW - Monte Carlo
KW - multi-physics
M3 - Conference article in proceedings
SN - 978-0-89448-700-2
SP - 926
EP - 937
BT - Proceedings
ER -