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Title: MCNP Models for Tokamak Cooling Water System Equipment Evaluations

Abstract

Heat generated in the ITER fusion reactor is deposited in the tokamak vacuum vessel, in-vessel components, and in the components of the neutral beam injector during plasma operations and during subsequent decay of activation products. This heat is managed by the tokamak cooling water system (TCWS). The stainless steel material in the integrated loop of blanket edge-localized mode vertical stabilization coils and divertor (IBED) components (e.g., piping, heat exchangers (HXs), and pumps) contains activation sources because of its exposure primarily to neutron radiation from the decay of 17N, which is a short-lived radionuclide produced by neutron capture reactions with oxygen nuclei in the IBED primary heat transfer system (PHTS) cooling water during plasma operations. A detailed geometry model of the IBED stainless steel components and neutron radiation sources is required for an accurate assessment of the gamma activation sources on level 3 of the tokamak building. In the baseline design, each of the eight IBED PHTS cooling trains has two shell-and-tube heat exchangers (HXs) connected in series. Because these HXs are very large and contain a large amount of radioactive water, the possibility of using compact HXs of the welded shell-and-plate type is under investigation. This paper presents two Montemore » Carlo N-Particle (MCNP) TCWS geometry models, one model for each HX type, along with the associated piping. These models were obtained by automatic geometry conversion from TCWS computer-aided design models. In conclusion, the TCWS geometry models and neutron source definitions were incorporated into a baseline MCNP model of the Tokamak Complex.« less

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1545229
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Fusion Science and Technology
Additional Journal Information:
Journal Volume: 75; Journal Issue: 6; Journal ID: ISSN 1536-1055
Publisher:
American Nuclear Society
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER; Tokamak cooling water system; heat exchanger

Citation Formats

Radulescu, Georgeta, Royston, Katherine E., Wilson, Stephen C., Van Hove, Walter A., Williamson, David E., and Kim, Seokho H. MCNP Models for Tokamak Cooling Water System Equipment Evaluations. United States: N. p., 2019. Web. doi:10.1080/15361055.2019.1589205.
Radulescu, Georgeta, Royston, Katherine E., Wilson, Stephen C., Van Hove, Walter A., Williamson, David E., & Kim, Seokho H. MCNP Models for Tokamak Cooling Water System Equipment Evaluations. United States. https://doi.org/10.1080/15361055.2019.1589205
Radulescu, Georgeta, Royston, Katherine E., Wilson, Stephen C., Van Hove, Walter A., Williamson, David E., and Kim, Seokho H. Tue . "MCNP Models for Tokamak Cooling Water System Equipment Evaluations". United States. https://doi.org/10.1080/15361055.2019.1589205. https://www.osti.gov/servlets/purl/1545229.
@article{osti_1545229,
title = {MCNP Models for Tokamak Cooling Water System Equipment Evaluations},
author = {Radulescu, Georgeta and Royston, Katherine E. and Wilson, Stephen C. and Van Hove, Walter A. and Williamson, David E. and Kim, Seokho H.},
abstractNote = {Heat generated in the ITER fusion reactor is deposited in the tokamak vacuum vessel, in-vessel components, and in the components of the neutral beam injector during plasma operations and during subsequent decay of activation products. This heat is managed by the tokamak cooling water system (TCWS). The stainless steel material in the integrated loop of blanket edge-localized mode vertical stabilization coils and divertor (IBED) components (e.g., piping, heat exchangers (HXs), and pumps) contains activation sources because of its exposure primarily to neutron radiation from the decay of 17N, which is a short-lived radionuclide produced by neutron capture reactions with oxygen nuclei in the IBED primary heat transfer system (PHTS) cooling water during plasma operations. A detailed geometry model of the IBED stainless steel components and neutron radiation sources is required for an accurate assessment of the gamma activation sources on level 3 of the tokamak building. In the baseline design, each of the eight IBED PHTS cooling trains has two shell-and-tube heat exchangers (HXs) connected in series. Because these HXs are very large and contain a large amount of radioactive water, the possibility of using compact HXs of the welded shell-and-plate type is under investigation. This paper presents two Monte Carlo N-Particle (MCNP) TCWS geometry models, one model for each HX type, along with the associated piping. These models were obtained by automatic geometry conversion from TCWS computer-aided design models. In conclusion, the TCWS geometry models and neutron source definitions were incorporated into a baseline MCNP model of the Tokamak Complex.},
doi = {10.1080/15361055.2019.1589205},
journal = {Fusion Science and Technology},
number = 6,
volume = 75,
place = {United States},
year = {Tue Apr 30 00:00:00 EDT 2019},
month = {Tue Apr 30 00:00:00 EDT 2019}
}

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Works referenced in this record:

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  • DOI: 10.2172/1210162

Status of the McCad geometry conversion tool and related visualization capabilities for 3D fusion neutronics calculations
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