Browse > Article
http://dx.doi.org/10.1016/j.net.2019.07.019

Design and simulation of a blanket module with high efficiency cooling system of tokamak focused on DEMO reactor  

Sadeghi, H. (Energy Engineering and Physics Department, Amirkabir University of Technology)
Amrollahi, R. (Energy Engineering and Physics Department, Amirkabir University of Technology)
Zare, M. (Energy Engineering and Physics Department, Amirkabir University of Technology)
Fazelpour, S. (Energy Engineering and Physics Department, Amirkabir University of Technology)
Publication Information
Nuclear Engineering and Technology / v.52, no.2, 2020 , pp. 323-327 More about this Journal
Abstract
In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed. In the proposed design, it is adequate to enrich up to 40% 6Li. Total tritium breeding ratio of 1.12 is achieved. The temperature of helium as coolant gas never exceed 687℃. As regards the tolerable temperature of beryllium (650℃), the design of blanket module is done in the way that beryllium temperature never exceed 600℃. The main feature of this design indicates the temperature of helium coolant is higher than other proposed models for blanket module, therefore power of electricity generation will increase.
Keywords
Fusion; Breeding blanket; Tritium; Tokamak; Helium-cooled pebble bed (HCPB);
Citations & Related Records
연도 인용수 순위
  • Reference
1 H. Sadeghi, et al., Simulation of dense plasma focus devices to produce N-13 efficiently, Laser Part. Beams (2019) 1-8.
2 R. Amrollahi, et al., Alborz tokamak system engineering and design, Fusion Eng. Des. 141 (2019) 91-100.   DOI
3 S. Fazelpour, et al., Design and simulation of NBI heating system using high dense helicon plasma source for Damavand Tokamak, Fusion Eng. Des. 137 (2018) 152-164.   DOI
4 H. Sadeghi, M. Habibi, Designing a compact, portable and high efficiency reactor 33 (No. 1) (2019) 13, https://doi.org/10.1142/S0217732319502079, 1950207.
5 T. Ihli, et al., Review of blanket designs for advanced fusion reactors, Fusion Eng. Des. 83 (2008) 912-919.   DOI
6 D. Mcmorrow, Tritium, Internal Report, The MITRE Corporation, 2011.
7 W.Biel, Tritium Breeding and blanket technology, DPG school "the physics of ITER" Bad Honnef, 26.09.2014
8 R. Andreani, et al., Fusion Eng. Des. 81 (1-7) (2006) 25-32.   DOI
9 Y. Poitevin, The tritium breeding blankets for fusion reactors, 2011. Swiss Nuclear Forum, CRPP/Lausanne March-23.
10 W. Meier, Assessment of Tritium Breeding Blankets from a Systems Perspective e Status Report, Department of Energy by Lawrence Livermore National Laboratory, 2014.
11 A.R. Raffray, et al., Breeding blanket concepts for fusion and materials requirements, J. Nucl. Mater. 307-311 (2002) 21-30.   DOI
12 Z. Xu, et al., Development of a DEMO helium cooled pebble bed (HCPB) breeder unit featured in flat plates with meandering channels, Wissenschaftliche Berichte (August 2006). FZKA-7181 ISSN 0947-8620.
13 N. Zandi, et al., Blanket simulation and tritium breeding ratio calculation for ITER reactor, J. Fusion Energy 34 (2015) 1365.
14 A. Ying, Status and perspective of the R&D on ceramic breeder materials for testing in ITER, J. Nucl. Mater. 367-370 (2007) 1281-1286.   DOI
15 R. Lasser "Structural materials for DEMO: development, testing and modelling", 24th SOFT, 11-15 Sept 2006, Warsaw.
16 D. Aquaro, et al., Adaptation of the HCPB DEMO TBM as breeding blanket for ITER: neutronic and thermal analyses, Fusion Eng. Des. 82 (2007) 2226-2232.   DOI
17 P. Norajitra, et al., Conceptual design of the EU dual-coolant blanket (model C), in: 20th IEEE/NPSS Symposium on Fusion Engineering (SOFE). San Diego, CA, USA, 2003, p. 4.
18 A.R. Raffray, et al., Ceramic breeder blanket for ARIES-CS, Fusion Sci. Technol. 47 (4) (2005) 1068-1073.   DOI
19 H. Sadeghi, M. Habibi, Design and simulation of a blanket module for TOKAMAK reactors, Mod. Phys. Lett. A (2019), https://doi.org/10.1142/S0217732319501037.
20 H. Sadeghi, et al., Laser Part. Beams (2017) 1-5, https://doi.org/10.1017/S0263034617000386.
21 H. Sadeghi, et al., High efficiency focus neutron generator, Plasma Phys. Control. Fusion (2017), https://doi.org/10.1088/1361-6587/aa8be0.