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.
|