Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis
Abstract
The ITER International Organization has developed a number of reference Monte Carlo NParticle (MCNP) models including the tokamak machine Cmodel, the Tokamak Complex model, and the neutral beam injection (NBI) systems model. The Tokamak Complex model primarily describes building structures beyond the bioshield. Representation of the tokamak and its systems are not included in this model. The Oak Ridge National Laboratory Radiation Transport Group has conducted two ITER neutronic analysis model integrations: (1) integration of the tokamak Cmodel with the Tokamak Complex model for shutdown dose rate characterization in Port Cell 16 at level B1, and (2) integration of the NBI model with the Tokamak Complex model for estimating the spatial distribution of biological dose rate at levels L1, L2, and L3 of the Tokamak Complex. The integrated models were further extended to include models of system components that are essential to the neutronic analyses. Furthermore, this paper presents the approach and computer tools used to integrate existing reference models, describes the additional design details implemented in the integrated models, and provides representative neutronic calculations based on the extended models.
 Authors:

 Oak Ridge National Lab. (ORNL) Radiation Transport Group, Oak Ridge, TN (United States)
 Publication Date:
 Research Org.:
 Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
 Sponsoring Org.:
 USDOE
 OSTI Identifier:
 1484140
 Grant/Contract Number:
 AC0500OR22725
 Resource Type:
 Accepted Manuscript
 Journal Name:
 Fusion Science and Technology
 Additional Journal Information:
 Journal Volume: 74; Journal Issue: 4; Journal ID: ISSN 15361055
 Publisher:
 American Nuclear Society
 Country of Publication:
 United States
 Language:
 English
 Subject:
 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER; neutronic analyses; model integration; Cmodel; Tokamak Complex model
Citation Formats
Yang, Jinan, Wilson, Stephen C., Mosher, Scott W., and Radulescu, Georgeta. Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis. United States: N. p., 2018.
Web. doi:10.1080/15361055.2018.1493325.
Yang, Jinan, Wilson, Stephen C., Mosher, Scott W., & Radulescu, Georgeta. Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis. United States. https://doi.org/10.1080/15361055.2018.1493325
Yang, Jinan, Wilson, Stephen C., Mosher, Scott W., and Radulescu, Georgeta. Wed .
"Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis". United States. https://doi.org/10.1080/15361055.2018.1493325. https://www.osti.gov/servlets/purl/1484140.
@article{osti_1484140,
title = {Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis},
author = {Yang, Jinan and Wilson, Stephen C. and Mosher, Scott W. and Radulescu, Georgeta},
abstractNote = {The ITER International Organization has developed a number of reference Monte Carlo NParticle (MCNP) models including the tokamak machine Cmodel, the Tokamak Complex model, and the neutral beam injection (NBI) systems model. The Tokamak Complex model primarily describes building structures beyond the bioshield. Representation of the tokamak and its systems are not included in this model. The Oak Ridge National Laboratory Radiation Transport Group has conducted two ITER neutronic analysis model integrations: (1) integration of the tokamak Cmodel with the Tokamak Complex model for shutdown dose rate characterization in Port Cell 16 at level B1, and (2) integration of the NBI model with the Tokamak Complex model for estimating the spatial distribution of biological dose rate at levels L1, L2, and L3 of the Tokamak Complex. The integrated models were further extended to include models of system components that are essential to the neutronic analyses. Furthermore, this paper presents the approach and computer tools used to integrate existing reference models, describes the additional design details implemented in the integrated models, and provides representative neutronic calculations based on the extended models.},
doi = {10.1080/15361055.2018.1493325},
journal = {Fusion Science and Technology},
number = 4,
volume = 74,
place = {United States},
year = {2018},
month = {8}
}
Web of Science
Figures / Tables:
Works referenced in this record:
Status of the McCad geometry conversion tool and related visualization capabilities for 3D fusion neutronics calculations
journal, October 2013
 Große, D.; Fischer, U.; Kondo, K.
 Fusion Engineering and Design, Vol. 88, Issue 910
ADVANTG An Automated Variance Reduction Parameter Generator, Rev. 1
report, August 2015
 Mosher, Scott W.; Johnson, Seth R.; Bevill, Aaron M.
Works referencing / citing this record:
Algorithmic Improvements to MCNP5 for HighResolution Fusion Neutronics Analyses
journal, August 2018
 Mosher, Scott W.; Wilson, Stephen C.
 Fusion Science and Technology, Vol. 74, Issue 4
Figures / Tables found in this record: