Abstract
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.
| Original language | English |
|---|---|
| Title of host publication | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 |
| Publisher | American Nuclear Society (ANS) |
| Pages | 926-937 |
| ISBN (Print) | 978-0-89448-700-2 |
| Publication status | Published - 2013 |
| MoE publication type | A4 Article in a conference publication |
| 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 |
Conference
| Conference | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 |
|---|---|
| Abbreviated title | M&C 2013 |
| Country/Territory | United States |
| City | Sun Valley, ID |
| Period | 5/05/13 → 9/05/13 |
Keywords
- coupled calculation
- material properties
- Monte Carlo
- multi-physics