Blanket Simulation and Tritium Breeding Ratio Calculation for ITER Reactor

被引：7

作者：

Zandi, N. ^{[1
]}

Sadeghi, H. ^{[1
]}

Habibi, M. ^{[1
]}

Jalali, I. ^{[1
]}

Zare, M. ^{[1
]}

机构：

[1] Amirkabir Univ Technol, Dept Energy Engn & Phys, Tehran, Iran

来源：

JOURNAL OF FUSION ENERGY | 2015年 / 34卷 / 06期

关键词：

Tritium breeding ratio; HCPB; Blanket; Tritium self-sufficiency;

D O I：

10.1007/s10894-015-9970-z

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium fusion power reactor using Monte Carlo MCNPX is done. To this end Li4SiO4 was considered as the blanket module. In order to improve the distribution of power density in the blanket module, an arrangement of the neutron multiplier Be in the breeding zone has been optimized. Total TBR of 1.14 is achieved. Finally helium cooled pebble bed was designed as cooling system using COMSOL Multiphysics simulator.

引用

页码：1365 / 1368

页数：4

共 50 条

[11] Optimization of tritium breeding ratio in ARC reactor
Segantin, Stefano
Testoni, Raffaella
Hartwig, Zachary
Whyte, Dennis
Zucchetti, Massimo
FUSION ENGINEERING AND DESIGN, 2020, 154
[12] Deuterium ion irradiation for tritium breeding material and evaluation for tritium inventories in test blanket module and blanket of a demonstration reactor
Hino, T.
Shibata, H.
Yamauchi, Y.
Nobuta, Y.
Suzuki, S.
Akiba, M.
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) : 713 - 717
[13] INVESTIGATIONS OF LITHIUM CARBIDE AS TRITIUM BREEDING MATERIAL FOR BLANKET OF THE FUSION REACTOR
Alenina, M. V.
Kolotov, V. P.
Platov, Yu. M.
PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2013, (05): : 120 - 124
[14] A simulation study of thermal breeding of tritium at low temperatures in a D-T fusion reactor blanket
Goswami, M
Ahmed, F
Gupta, S
ANNALS OF NUCLEAR ENERGY, 1998, 25 (1-3) : 181 - 187
[15] Sensitivity and uncertainty analysis for the tritium breeding ratio of a DEMO fusion reactor with a helium cooled pebble bed blanket
Nunnenmann, Elena
Fischer, Ulrich
Stieglitz, Robert
ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, 2017, 146
[16] Low-temperature tritium releasing ceramics as potential materials for the ITER breeding blanket
Roux, N
Avon, J
Floreancig, A
Mougin, J
Rasneur, B
Ravel, S
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 1431 - 1435
[17] Optimization of Tritium Breeding and Shielding Analysis to Plasma in ITER Fusion Reactor
Rosidah, Indah M.
Suud, Zaki
Yazid, Putranto Ilham
5TH INTERNATIONAL CONFERENCE ON MATHEMATICS AND NATURAL SCIENCES (ICMNS 2014), 2015, 1677
[18] EFFECT OF BLANKET STRUCTURE ON TRITIUM BREEDING RATIO IN FUSION-REACTORS
MAKI, K
OKAZAKI, T
NUCLEAR TECHNOLOGY-FUSION, 1983, 4 (03): : 468 - 478
[19] On monitoring the tritium-breeding ratio in a fusion reactor
Kapyshev, V.
Kovalenko, V.
Poliksha, V.
Sidorov, A.
Strebkov, Yu.
Yukhnov, N.
PLASMA DEVICES AND OPERATIONS, 2008, 16 (02): : 135 - 145
[20] A SIMULATION STUDY FOR HYDROGEN ISOTOPE DISTILLATION-COLUMNS IN THE TRITIUM BREEDING BLANKET SYSTEM OF A FUSION-REACTOR
KINOSHITA, M
YOSHIDA, H
TAKESHITA, H
FUSION TECHNOLOGY, 1986, 10 (03): : 462 - 473

← 1 2 3 4 5 →