### 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 |
---|---|

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 |

Externally published | Yes |

### Fingerprint

### 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

*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.

Research output: Contribution to journal › Article

*Fusion Engineering and Design*, vol. 81, no. 8-14 PART B, pp. 1239-1244. https://doi.org/10.1016/j.fusengdes.2005.09.057

}

TY - JOUR

T1 - Neutronics analysis for a compact reversed shear tokamak CREST

AU - Huang, Q.

AU - Zheng, S.

AU - Lu, L.

AU - Hiwatari, R.

AU - Asaoka, Y.

AU - Okano, Kunihiko

AU - Ogawa, Y.

PY - 2006/2

Y1 - 2006/2

N2 - 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.

AB - 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.

KW - 3D calculations

KW - CREST

KW - Neutronics

UR - http://www.scopus.com/inward/record.url?scp=32444432530&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=32444432530&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2005.09.057

DO - 10.1016/j.fusengdes.2005.09.057

M3 - Article

AN - SCOPUS:32444432530

VL - 81

SP - 1239

EP - 1244

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

IS - 8-14 PART B

ER -