### 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/m^{2} 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 language | English |
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Pages (from-to) | 1239-1244 |

Number of pages | 6 |

Journal | Fusion Engineering and Design |

Volume | 81 |

Issue number | 8-14 PART B |

DOIs | |

Publication status | Published - 2006 Feb 1 |

Event | Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B - Duration: 2005 May 22 → 2005 May 27 |

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### Keywords

- 3D calculations
- CREST
- Neutronics

### ASJC Scopus subject areas

- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering

### Cite this

*Fusion Engineering and Design*,

*81*(8-14 PART B), 1239-1244. https://doi.org/10.1016/j.fusengdes.2005.09.057