Neutronics analysis for a compact reversed shear tokamak CREST

Q. Huang, S. Zheng, L. Lu, R. Hiwatari, Y. Asaoka, Kunihiko Okano, Y. Ogawa

Research output: Contribution to journalArticle

15 Citations (Scopus)

Abstract

The compact reversed shear tokamak CREST is a conceptual tokamak reactor design with high β plasma, high thermal efficiency, competitive cost and water-cooled ferritic steel components. In this manuscript neutronics analysis on CREST is presented based on the three-dimensional (3D) model and calculations by MCNP/4C code and FENDL/2.0 data library. The comparison among the results of tritium breeding ratio (TBR) for the one-dimensional (1D), two-dimensional (2D) and 3D calculations shows that the results are consistent with each other. The system would be tritium self-sufficient when considering the blanket coverage fraction, etc. and even some uncertainty. It has an energy multiplication of 1.38. The maximum neutron wall loading and maximum damage rate at the first wall (FW) are 6.30 MW/m2 and 51.9 dpa/FPY, respectively. The FW material needs to be replaced every 3.8 years of operation with an availability of 75% if the neutron damage of ferritic steel is assumed to limit to 150 dpa. The total nuclear heat for TF coils is under the limit for TF coils in ITER case. The nuclear heat density for TF coils at the mid-plane is roughly the same as the limit for ITER.

Original languageEnglish
Pages (from-to)1239-1244
Number of pages6
JournalFusion Engineering and Design
Volume81
Issue number8-14 PART B
DOIs
Publication statusPublished - 2006 Feb
Externally publishedYes

Fingerprint

Tritium
Ferritic steel
Neutrons
Availability
Plasmas
Water
Hot Temperature
Costs
Uncertainty

Keywords

  • 3D calculations
  • CREST
  • Neutronics

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering

Cite this

Huang, Q., Zheng, S., Lu, L., Hiwatari, R., Asaoka, Y., Okano, K., & Ogawa, Y. (2006). Neutronics analysis for a compact reversed shear tokamak CREST. Fusion Engineering and Design, 81(8-14 PART B), 1239-1244. https://doi.org/10.1016/j.fusengdes.2005.09.057

Neutronics analysis for a compact reversed shear tokamak CREST. / Huang, Q.; Zheng, S.; Lu, L.; Hiwatari, R.; Asaoka, Y.; Okano, Kunihiko; Ogawa, Y.

In: Fusion Engineering and Design, Vol. 81, No. 8-14 PART B, 02.2006, p. 1239-1244.

Research output: Contribution to journalArticle

Huang, Q, Zheng, S, Lu, L, Hiwatari, R, Asaoka, Y, Okano, K & Ogawa, Y 2006, 'Neutronics analysis for a compact reversed shear tokamak CREST', Fusion Engineering and Design, vol. 81, no. 8-14 PART B, pp. 1239-1244. https://doi.org/10.1016/j.fusengdes.2005.09.057
Huang Q, Zheng S, Lu L, Hiwatari R, Asaoka Y, Okano K et al. Neutronics analysis for a compact reversed shear tokamak CREST. Fusion Engineering and Design. 2006 Feb;81(8-14 PART B):1239-1244. https://doi.org/10.1016/j.fusengdes.2005.09.057
Huang, Q. ; Zheng, S. ; Lu, L. ; Hiwatari, R. ; Asaoka, Y. ; Okano, Kunihiko ; Ogawa, Y. / Neutronics analysis for a compact reversed shear tokamak CREST. In: Fusion Engineering and Design. 2006 ; Vol. 81, No. 8-14 PART B. pp. 1239-1244.
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