Analysis on burnup step effect for evaluating reactor criticality and fuel breeding ratio

2014 ◽  
Author(s):  
Geby Saputra ◽  
Aditya Rizki Purnama ◽  
Sidik Permana ◽  
Mitsutoshi Suzuki
Keyword(s):  
Reactor Criticality ◽  
Step Effect ◽  
Breeding Ratio

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.

Spin-glass state induced low field magnetization-step effect in a Hg1−x Mn x Te single crystal

2016 ◽  
Vol 253 (10) ◽  
pp. 2015-2019
Author(s):  
Liangqing Zhu ◽  
Jun Shao ◽  
Liang Zhu ◽  
Xiren Chen ◽  
Tie Lin ◽  
...  
Keyword(s):  
Single Crystal ◽  
Spin Glass ◽  
Spin Glass State ◽  
Glass State ◽  
Low Field ◽  
Field Magnetization ◽  
Step Effect

scholarly journals Cross-section sensitivity of breeding ratio in a fusion-reactor blanket

1973 ◽  
Author(s):  
D. E. Bartine ◽  
Jr., R. G. Alsmiller ◽  
E. M. Oblow ◽  
F. R. Mynatt
Keyword(s):  
Cross Section ◽  
Fusion Reactor ◽  
Fusion Reactor Blanket ◽  
Breeding Ratio

scholarly journals THE BREEDING RATIO OF A PLUTOMIUM LOADING IN EBR-I

1964 ◽  
Author(s):  
R.R. Smith ◽  
R.O. Haroldsen ◽  
R.E. Horne ◽  
R.G. Matlock
Keyword(s):  
Breeding Ratio

Breeding Ratio For Fast Reactors

1971 ◽  
Vol 10 (2) ◽  
pp. 101-102
Author(s):  
P. Goldschmidt
Keyword(s):  
Fast Reactors ◽  
Breeding Ratio

Influence of geometry in TRIGA reactor criticality calculation and reactivity determination using Serpent 2 and MCNPX codes

2017 ◽  
Vol 11 (2) ◽  
pp. 146
Author(s):  
Sincler Peixoto De Meireles ◽  
Amir Zacarias Mesquita ◽  
Mauricio Quelhas Antolin ◽  
Daniel De Almeida Magalho ◽  
es Campolina ◽  
...  
Keyword(s):  
Triga Reactor ◽  
Reactor Criticality ◽  
Reactivity Determination

Design and simulation of a blanket module for TOKAMAK reactors

2019 ◽  
Vol 34 (13) ◽  
pp. 1950103 ◽  
Author(s):  
H. Sadeghi ◽  
M. Habibi
Keyword(s):  
Comsol Multiphysics ◽  
Fusion Reactors ◽  
Tritium Breeding ◽  
Mcnpx Code ◽  
Self Sufficiency ◽  
Proposed Model ◽  
Tokamak Reactors ◽  
Breeding Ratio ◽  
Neutron Multiplier ◽  
Temperature And Pressure

In this paper, we simulated an appropriate model for an advanced breeding blanket of future TOKAMAK fusion reactors with solid breeder (Li4SiO4) building material in the form of pebble beds, ODS ferritic steel as structural material and Beryllium as neutron multiplier. With the MCNPX code, the efficiency of this proposed model for the production and self-sufficiency of tritium was investigated. Total tritium breeding ratio of 1.15 is achieved. The helium-cooled pebble bed system and parameters of temperature and pressure are investigated by COMSOL multiphysics simulating software. The temperature of helium as cooling gas never exceeded 530[Formula: see text]C and the tolerable temperature of beryllium was obtained at 650[Formula: see text]C. In the proposed design, it is adequate to enrich the 6Li to 40%.

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