Results 201 to 210 of about 3,515 (225)

Modeling of the GELINA neutron target using coupled electron–photon–neutron transport with the MCNP4C3 code

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2004
Abstract Coupled electron–photon–neutron transport calculations were performed with the Monte Carlo code MCNP4C3 to model the GELINA neutron target. Our calculations were compared with measurements of the direct and moderated flux distributions and agreement was achieved within 20%.
M. Flaska, A. Borella, D. Lathouwers, L.C. Mihailescu, W. Mondelaers, A.J.M. Plompen, H. van Dam, T.H.J.J. van der Hagen   +7 more
openaire   +1 more source

Calibration of neutron yield activation measurements at JET using MCNP and FURNACE neutron transport codes

Fusion Engineering and Design, 1989
Neutron transport calculations have been performed using fluence ray tracing (FURNACE code) and Monte Carlo particle trajectory sampling methods (MCNP code) in order to determine the neutron fluence and energy distributions at different locations in the JET tokamak.
M. Pillon, K.A. Verschuur, O.N. Jarvis, J. Källne, M. Martone   +4 more
openaire   +1 more source

Vectorization and multitasking with a Monte Carlo code for neutron transport problems

2006
This paper summarizes two improvements of a Monte Carlo code by resorting to vectorization and multitasking techniques.
openaire   +1 more source

3D Neutron Transport PWR Full-core Calculation with RMC code

SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014
Nowadays, there are more and more interests in the use of Monte Carlo codes to calculate the detailed power density distributions in full-core reactors. With the Inspur TS1000 HPC Server of Tsinghua University, several calculations have been done based on the EDF 3D Neutron Transport PWR Full-core benchmark through large-scale parallelism.
Yishu Qiu, Ding She, Xiao Fan, Kan Wang, Zeguang Li, Jingang Liang, Hadrien Leroyer   +6 more
openaire   +1 more source

Outer Iteration Scaling in Neutron Transport Codes

Nuclear Science and Engineering, 1970
B. E. Clancy, I. J. Donnelly
openaire   +1 more source

Neutron Transport Modeling using Monte Carlo Codes

Neutron Transport Modeling using Monte Carlo Codes, 2022
openaire   +1 more source

VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods

Annals of Nuclear Energy, 2022
Tengfei Zhang, Xiaojing Liu
exaly  

Development of a GPU-based three-dimensional neutron transport code

Annals of Nuclear Energy, 2022
Ao Zhang, Ming Dai, Maosong Cheng, Jianhui Wu, Jingen Chen   +4 more
openaire   +1 more source

Study on the acceleration of neutron transport code by GPU

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2012
ikemoto, daisuke, kitada, takanori
openaire   +1 more source

Code Verification and Solution Verification framework in pin-resolved neutron transport code MPACT

Annals of Nuclear Energy, 2022
Jipu Wang, William R. Martin, Thomas J. Downar, Brendan Kochunas, Nathan C. Andrews, Lindsay Gilkey, Erik D. Walker, Benjamin S. Collins, Martin Pilch   +8 more
openaire   +1 more source