TY - GEN
T1 - XE-100 Modeling and Simulation for Neutronic Analysis in MCNP6.2
AU - Carter, Austin
AU - Lange, Travis
AU - Balestra, Paolo
AU - Strydom, Gerhard
AU - Sen, Sonat
AU - Wang, Raymond
N1 - Funding Information:
This manuscript was authored by Battelle Energy Alliance, LLC under Contract No. DEAC07-05ID14517 with the U.S. Department of Energy. The U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. Government purposes. This research made use of the resources of the High Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Publisher Copyright:
© 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.
PY - 2022
Y1 - 2022
N2 - XE-100 is a Generation IV high-temperature, helium-cooled, graphite-moderated, pebble-bed reactor (HTGR). As part of the pathway toward a conceptually designing and licensing this reactor, an independent Monte Carlo model was created in MCNP6.2, and several distinct neutronic analyses were then performed. The double heterogeneity of TRISO fuel within graphite pebbles introduces unique modeling challenges related to particle and pebble clipping. The results show that for neutron and photon heating of ex-core components such as the reflector, RCSS, CB, the model that contains clipping produces higher heating values. It is therefore concluded that removing clipping via compression of the particles and pebbles within the model distributes the neutrons and gammas preferentially toward the core center, and reduces the heating that is experienced toward the reactor periphery. Thus, the most conservative model for ex-core heating contains particle and pebble clipping. Also presented are results on the impact of chamfers that exist on the corners of graphite reflector blocks. As these chamfers could potentially create streaming paths, the neutron and gamma flux from the core to the core barrel (CB) were analyzed. It was determined that the chamfers do not significantly impact the neutron or gamma signatures on the CB, in that the shape of the neutron and photon flux on a detector imposed on the CB shows no preferential streaming path.
AB - XE-100 is a Generation IV high-temperature, helium-cooled, graphite-moderated, pebble-bed reactor (HTGR). As part of the pathway toward a conceptually designing and licensing this reactor, an independent Monte Carlo model was created in MCNP6.2, and several distinct neutronic analyses were then performed. The double heterogeneity of TRISO fuel within graphite pebbles introduces unique modeling challenges related to particle and pebble clipping. The results show that for neutron and photon heating of ex-core components such as the reflector, RCSS, CB, the model that contains clipping produces higher heating values. It is therefore concluded that removing clipping via compression of the particles and pebbles within the model distributes the neutrons and gammas preferentially toward the core center, and reduces the heating that is experienced toward the reactor periphery. Thus, the most conservative model for ex-core heating contains particle and pebble clipping. Also presented are results on the impact of chamfers that exist on the corners of graphite reflector blocks. As these chamfers could potentially create streaming paths, the neutron and gamma flux from the core to the core barrel (CB) were analyzed. It was determined that the chamfers do not significantly impact the neutron or gamma signatures on the CB, in that the shape of the neutron and photon flux on a detector imposed on the CB shows no preferential streaming path.
KW - HTGR
KW - MCNP
KW - Pebble Bed
KW - Variance Reduction
KW - XE-100
UR - https://www.scopus.com/pages/publications/85179831977
UR - https://www.mendeley.com/catalogue/b3d571bd-6637-3bd8-96ae-bb5125481ac0/
U2 - 10.13182/PHYSOR22-37642
DO - 10.13182/PHYSOR22-37642
M3 - Conference contribution
AN - SCOPUS:85179831977
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
SP - 58
EP - 67
BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
PB - American Nuclear Society
T2 - 2022 International Conference on Physics of Reactors, PHYSOR 2022
Y2 - 15 May 2022 through 20 May 2022
ER -