TY - JOUR
T1 - Benchmark of Serpent-2 with MCNP
T2 - Application to European DEMO HCPB breeding blanket
AU - Lu, Yudong
AU - Zhou, Guangming
AU - Hernández, Francisco A.
AU - Pereslavtsev, Pavel
AU - Leppänen, Jaakko
AU - Ye, Minyou
N1 - Funding Information:
This work has been funded by the National Key Research, Development Program of China (Grant No.: 2017YFE0301501 and No.: 2017YFE0301305) and China Scholarship Council (No.: 201806340163). The work was completed during Yudong Lu's research stay at Karlsruhe Institute of Technology (KIT). The authors would like to thank Drs. Lorenzo V. Boccaccini and Ulrich Fischer from KIT for valuable discussions. The authors would like to thank Dr. Andrew Davis from UKAEA for making the csg2csg conversion tool freely accessible.
Publisher Copyright:
© 2020 Elsevier B.V.
PY - 2020/6
Y1 - 2020/6
N2 - Magnetic confinement fusion reactors such as the European fusion demonstration reactor (EU DEMO) have a very complex geometry, which makes the modelling of the nuclear analyses rather tedious and time consuming. The Monte Carlo neutron transport code Serpent-2 developed by VTT in Finland, is able to directly import CAD geometry, then is considered an attractive alternative to the Monte Carlo N-Particle Transport code (MCNP) for its application on fusion reactors. In the first step, a comparison activity is carried out to benchmark the Serpent-2 with MCNP calculations. Both Serpent-2 and MCNP are used to perform the 3D Monte Carlo neutron and photon coupled transport making use of the EU-DEMO BL2017 model and a grid discrete volume source. A very useful conversion tool (called csg2csg) developed by UKAEA researchers was used to translate the MCNP input model to the Serpent-2 input model. The nuclear performance of the EU DEMO Helium Cooled Pebble Bed breeding blanket, such as tritium breeding ratio (TBR), neutron and photon flux spectra, and nuclear heating are analyzed, and the corresponding results are compared between Serpent-2 and MCNP. This study shows that Serpent-2 is suitable for the application of nuclear analysis for the EU DEMO HCPB breeding blanket.
AB - Magnetic confinement fusion reactors such as the European fusion demonstration reactor (EU DEMO) have a very complex geometry, which makes the modelling of the nuclear analyses rather tedious and time consuming. The Monte Carlo neutron transport code Serpent-2 developed by VTT in Finland, is able to directly import CAD geometry, then is considered an attractive alternative to the Monte Carlo N-Particle Transport code (MCNP) for its application on fusion reactors. In the first step, a comparison activity is carried out to benchmark the Serpent-2 with MCNP calculations. Both Serpent-2 and MCNP are used to perform the 3D Monte Carlo neutron and photon coupled transport making use of the EU-DEMO BL2017 model and a grid discrete volume source. A very useful conversion tool (called csg2csg) developed by UKAEA researchers was used to translate the MCNP input model to the Serpent-2 input model. The nuclear performance of the EU DEMO Helium Cooled Pebble Bed breeding blanket, such as tritium breeding ratio (TBR), neutron and photon flux spectra, and nuclear heating are analyzed, and the corresponding results are compared between Serpent-2 and MCNP. This study shows that Serpent-2 is suitable for the application of nuclear analysis for the EU DEMO HCPB breeding blanket.
KW - Fusion
KW - Monte Carlo
KW - Neutronics
KW - Serpent
UR - http://www.scopus.com/inward/record.url?scp=85080032643&partnerID=8YFLogxK
U2 - 10.1016/j.fusengdes.2020.111583
DO - 10.1016/j.fusengdes.2020.111583
M3 - Article
AN - SCOPUS:85080032643
SN - 0920-3796
VL - 155
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
M1 - 111583
ER -
