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Title: Multiphysics modeling of the FW/Blanket of the U.S. fusion nuclear science facility (FNSF)

Journal Article · · Fusion Engineering and Design
 [1];  [2];  [1];  [3];  [3];  [4]
  1. Univ. of California, Los Angeles, CA (United States)
  2. Univ. of California, San Diego, CA (United States)
  3. Univ. of Wisconsin, Madison, WI (United States)
  4. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
+ Show Author Affiliations

The dual coolant lead-lithium (DCLL) blanket concept, which is utilized in the Fusion Nuclear Science Facility (FNSF) conceptual design, is based on a helium-cooled first wall and blanket structure with RAFS (Reduced Activation Ferritic Steel) and a self-cooled LiPb breeding zone. The objective of this work is to develop a multiphysics modeling process in order to optimize the design and achieve long lifetime, maintainability, and high reliability. 3D finite element multiphysics modeling of the DCLL first wall and blanket (midplane of one sector) has been performed using COMSOL 5.2. The multiphysics aspect of the design is demonstrated via coupling of Computational Fluid Dynamics (CFD), conjugate heat transfer and solid mechanics. Both normal and off-normal loading conditions have been analyzed. The results of velocity, pressure, and temperature distributions of helium flow, as well as the primary and thermal stress of the structure were obtained. This was followed by determination of the factors of safety along three critical paths based on the ITER Structural Design Criteria for In-vessel Components (ISDC-IC). We show here that the structural design meets the ITER-ISDC design rules under both normal and off-normal operating conditions, though the safety factors under off-normal condition with 8 MPa helium pressure are marginal. Thus simple design optimization was conducted based on a parametric study on first wall dimensions to improve the design.

Research Organization:
Univ. of California, Los Angeles, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
FG02-03ER54708
OSTI ID:
1609494
Journal Information:
Fusion Engineering and Design, Vol. 135, Issue B; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 15 works
Citation information provided by
Web of Science

References (13)

ARIES-ACT2 DCLL Power Core Design and Engineering journal January 2015
Fusion power core engineering for the ARIES-ST power plant journal February 2003
Deformation mechanisms in ferritic/martensitic steels and the impact on mechanical design journal October 2013
Assessment of the DCLL TBM Thermostructural Response Based on ITER Design Criteria journal July 2011
Advanced power core system for the ARIES-AT power plant journal February 2007
Effect of ELMS and disruptions on FNSF plasma-facing components journal October 2018
TBM testing in ITER: Requirements for the development of predictive tools to describe corrosion-related phenomena in HCLL blankets towards DEMO journal August 2012
Overview of the Blanket Comparison and Selection Study journal July 1985
Thermohydraulics of rib-roughened helium gas running cooling channels for first wall applications journal November 2016
MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF journal October 2018
Overview of ITER-FEAT - The future international burning plasma experiment journal October 2001
Neutronics aspects of the FESS-FNSF journal October 2018
Materials design data for reduced activation martensitic steel type F82H journal November 2002

Figures / Tables (26)

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY