A neutron poison tritium breeding controller applied to a water cooled fusion reactor model

2014 ◽  
Vol 89 (7-8) ◽  
pp. 1190-1194 ◽  
Author(s):  
L.W.G. Morgan ◽  
L.W. Packer
Keyword(s):  
Fusion Reactor ◽  
Tritium Breeding ◽  
Reactor Model ◽  
Neutron Poison

scholarly journals Statistical Analysis of Tritium Breeding Ratio Deviations in the DEMO Due to Nuclear Data Uncertainties

2021 ◽  
Vol 11 (11) ◽  
pp. 5234
Author(s):  
Jin Hun Park ◽  
Pavel Pereslavtsev ◽  
Alexandre Konobeev ◽  
Christian Wegmann
Keyword(s):  
Monte Carlo ◽  
Fusion Reactor ◽  
Nuclear Data ◽  
Data File ◽  
Nuclear Model ◽  
Model Parameters ◽  
Tritium Breeding ◽  
Tritium Breeding Ratio ◽  
Nuclear Data Library ◽  
Breeding Ratio

For the stable and self-sufficient functioning of the DEMO fusion reactor, one of the most important parameters that must be demonstrated is the Tritium Breeding Ratio (TBR). The reliable assessment of the TBR with safety margins is a matter of fusion reactor viability. The uncertainty of the TBR in the neutronic simulations includes many different aspects such as the uncertainty due to the simplification of the geometry models used, the uncertainty of the reactor layout and the uncertainty introduced due to neutronic calculations. The last one can be reduced by applying high fidelity Monte Carlo simulations for TBR estimations. Nevertheless, these calculations have inherent statistical errors controlled by the number of neutron histories, straightforward for a quantity such as that of TBR underlying errors due to nuclear data uncertainties. In fact, every evaluated nuclear data file involved in the MCNP calculations can be replaced with the set of the random data files representing the particular deviation of the nuclear model parameters, each of them being correct and valid for applications. To account for the uncertainty of the nuclear model parameters introduced in the evaluated data file, a total Monte Carlo (TMC) method can be used to analyze the uncertainty of TBR owing to the nuclear data used for calculations. To this end, two 3D fully heterogeneous geometry models of the helium cooled pebble bed (HCPB) and water cooled lithium lead (WCLL) European DEMOs were utilized for the calculations of the TBR. The TMC calculations were performed, making use of the TENDL-2017 nuclear data library random files with high enough statistics providing a well-resolved Gaussian distribution of the TBR value. The assessment was done for the estimation of the TBR uncertainty due to the nuclear data for entire material compositions and for separate materials: structural, breeder and neutron multipliers. The overall TBR uncertainty for the nuclear data was estimated to be 3~4% for the HCPB and WCLL DEMOs, respectively.

A study of time-dependent, low energy (2 × 10-4 eV

1996 ◽  
Vol 31 (2) ◽  
pp. 117-125 ◽  
Author(s):  
Sanjay Gupta ◽  
Feroz Ahmed ◽  
Suresh Garg
Keyword(s):  
Fusion Reactor ◽  
Low Energy ◽  
Time Dependent ◽  
Tritium Breeding ◽  
Neutron Spectra

scholarly journals Study on fusion blanket with ceramic solid as tritium breeding material

2021 ◽  
Vol 2072 (1) ◽  
pp. 012004
Author(s):  
I R Maemunah ◽  
Z Su’ud ◽  
A Waris ◽  
D Irwanto
Keyword(s):  
Fusion Reactor ◽  
The Self ◽  
Tritium Breeding ◽  
Thermodynamic Behavior ◽  
Breeding Material ◽  
Self Sufficiency

Abstract Variation of solid ceramic breeding might be one of the excellent candidates in a fusion reactor. The LiAlO2, Li4SiO4, Li2O, and Li2ZrO3 show pretty good requirements in tritium breeding capability and thermodynamic behavior. Especially for LiAlO2 and Li2ZrO3, in which they could be possible to breed without neutron multiplying needed as blanket used generally in order to reach the self-sufficiency reactor. So that, it makes up the material could be possible as high-estimation breeder material.

scholarly journals Tritium Breeding Capability of Heliotron-H Fusion Reactor Blankets

1982 ◽  
Vol 19 (9) ◽  
pp. 762-764 ◽  
Author(s):  
Hideki NAKASHIMA ◽  
Masao OHTA ◽  
Atsuo IIYOSHI
Keyword(s):  
Fusion Reactor ◽  
Tritium Breeding

Preparation of Li4SiO4 Ceramic Pebbles by Agar Method Using Li2SiO3 and Li2CO3 as Raw Materials

2016 ◽  
Vol 697 ◽  
pp. 814-817 ◽  
Author(s):  
Mao Qiao Xiang ◽  
Ying Chun Zhang ◽  
Yun Zhang ◽  
Chao Fu Wang ◽  
Yong Hong Yu
Keyword(s):  
Fusion Reactor ◽  
Raw Materials ◽  
Lithium Concentration ◽  
Lithium Carbonate ◽  
Tritium Breeding ◽  
Preparation Technology ◽  
Agar Gel ◽  
Lithium Metasilicate ◽  
Lithium Orthosilicate ◽  
Tritium Release

Lithium-containing ceramic pebbles, the likeliest tritium breeders in the future, are needed in the fusion reactor blankets. Currently, lithium orthosilicate (Li4SiO4) has been widely studied for tritium breeding pebble as it has 1250 °C melting temperature, 0.54 g/cm3 lithium concentration, and excellent tritium release performance. For simplifying reaction mechanism and the preparation technology to tailor the properties, the Li4SiO4 breeders were produced with an agar-gel technology using stable and cheap lithium metasilicate and lithium carbonate as starting materials. In addition, the solid (the prepared powder and ager) and liquid (deionized water) weight ration of the green pebble was also evaluated. The crush load, density, and open porosity achieved 36 N, 89.3% TD, and 4.5 %, respectively.

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