scholarly journals The Application of the Combined Fission Matrix Theory in Fast Reactors

2021 ◽  
Vol 9 ◽  
Author(s):  
Donghao He ◽  
Tengfei Zhang ◽  
Xiaojing Liu
Keyword(s):  
High Efficiency ◽  
Matrix Theory ◽  
Neutron Transport ◽  
Thermal Reactor ◽  
Fast Reactors ◽  
Sodium Fast Reactor ◽  
The Monte Carlo Method ◽  
Transport Calculation ◽  
Rms Error ◽  
Transport Method

The combined fission matrix theory is a recently-developed hybrid neutron transport method. It features high efficiency, fidelity, and resolution whole-core transport calculation. The theory is based on the assumption that the fission matrix element ai,j is dominated by the property of the destination cell i. This assumption can be well explained in thermal reactors, and the combined fission matrix method has been validated in a series of thermal neutron system benchmarks. This work examines the feasibility of the combined fission matrix theory in fast reactors. The European Sodium Fast Reactor is used as the numerical benchmark. Compared to the Monte Carlo method, the combined fission matrix theory reports a 64 pcm keff difference and 8.3% 2D RMS error. The error is much larger than that in thermal reactors, and the correction ratio cannot significantly reduce the material discontinuity error in fast reactors. Overall, the combined fission matrix theory is more suited for thermal reactor transport calculations. Its application in fast reactors needs further developments.

The Deep-Coupling and Preprocessed Photon Transport Based on RMC Codes

2018 ◽  
Author(s):  
Pan Qingquan ◽  
Wang Kan
Keyword(s):  
Computational Complexity ◽  
Conventional Method ◽  
Neutron Transport ◽  
Nuclear Data ◽  
Photoelectric Effect ◽  
Photon Transport ◽  
Transport Calculation ◽  
Calculation Results ◽  
Transport Method ◽  
Photon Coupling

The conventional method for neutron-photon coupling transport calculation lacks of clear physical meanings, where the process of neutron transport and photon transport are independent, and only ensures the numbers of photons to be coupling with the neutrons. At the same time, when dealing with photoelectric effect, the nuclear data will be processed frequently, increasing the amount of calculation. By modifying the RMC codes, the deep-coupling and preprocessed photon transport is achieved. This new coupling method can satisfy the physical requirements and reduce the computational complexity while ensuring the accuracy of the calculation. At the same time, the preprocessing of the photoelectric effect nuclear data can accelerate the calculation without changing the calculation results. Through the deep-coupling and preprocessed photon transport method, the RMC codes can finished the high-precision shielding calculation. A typical LWR component is calculated with the new method, and the results prove the effectiveness.

scholarly journals NUMERICAL THERMAL MODEL OF AN INCANDESCENT LAMP FOR SATELLITES TESTING

2020 ◽  
pp. 50-58
Author(s):  
Dmitriy Kulikov ◽  
Keyword(s):  
Mathematical Modeling ◽  
Thermal Model ◽  
High Efficiency ◽  
Complex Problem ◽  
Thermal Design ◽  
Halogen Lamp ◽  
Quality Model ◽  
Good Convergence ◽  
The Monte Carlo Method ◽  
Model Generator

In the present article the author gives the results work to create a numerical thermal model of infrared (IR) emitter on the base of tubular halogen lamp (THL) KGT-220-1300, as one of the elements of the equipment used when conducting thermal vacuum tests (TVT) of satellites. As a tool to solve complex problem of heat transfer used software Thermal Model Generator. Variants of calculations for the operation of the lamp at different voltages are carried out. The results of mathematical modeling using band approximation of the properties of the system elements in combination with the Monte Carlo method in solving the problem of heat exchange by radiation showed high efficiency. The performed analysis of the correctness of the results showed good convergence with the data of previous experiments on measuring the temperature of the quartz bulb, which confirms the reliability of the results. Getting a high-quality model of this type at the disposal of satellite thermal engineer is an important step in the complex work aimed at conducting end-to-end mathematical modeling of satellite thermal design, and will also solve a number of issues related to the methodological support of TVT, their implementation and optimization.

Large Electro-Magnetic Pump Design for Application in the ASTRID Sodium-Cooled Fast Reactor

2014 ◽  
Author(s):  
Rie Aizawa ◽  
Tetsu Suzuki ◽  
Guy Laffont ◽  
Frédéric Rey
Keyword(s):  
Fast Reactor ◽  
High Efficiency ◽  
Operating Conditions ◽  
Joint Work ◽  
Main Concept ◽  
Pump Design ◽  
Sodium Fast Reactor ◽  
Technological Developments ◽  
Electro Magnetic ◽  
Collaboration Agreement

Within the framework of the French Sodium Fast Reactor (SFR) prototype called ASTRID (Advance Sodium Technological Reactor for Industrial Demonstration), an application of Large capacity Electro-Magnetic Pumps (LEMP) is considered as a main concept of the circulating pump on intermediate sodium circuits. The use of LEMP has several merits in the design of reactor, operation, and maintenance. Furthermore, high efficiency is acquired when heat-resistant coil insulation is used for this LEMP. Nevertheless, some theoretical and technological developments have to be carried out in order to validate the design tools by taking into account Magneto Hydro Dynamic (MHD) phenomena and the applicability of the LEMP to ASTRID steady state and transient operating conditions. In this aim, a collaboration agreement between the CEA and TOSHIBA Corporation came into force in April 2012 to carry out a joint work program on the ASTRID EMP design and development. This paper describes the dedicated design studies and experimental activities for the LEMP development within the framework of the CEA-TOSHIBA collaboration.

scholarly journals Validation of the code package MCPV adapted for neutron transport calculation within WWER-440 reactor near-vessel space

2019 ◽  
Vol 20 (2) ◽  
pp. 153-158
Author(s):  
O.M. Pugach ◽  
◽  
S.M. Pugach ◽  
V.L. Diemokhin ◽  
V.N. Bukanov ◽  
...  
Keyword(s):  
Neutron Transport ◽  
Transport Calculation

scholarly journals High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor

2021 ◽  
Vol 253 ◽  
pp. 04029
Author(s):  
Edoardo L. Brunetto ◽  
Fanny Vitullo ◽  
Vincent Lamirand ◽  
Klemen Ambrožič ◽  
Daniel Godat ◽  
...  
Keyword(s):  
Reaction Rate ◽  
Detection System ◽  
Neutron Transport ◽  
Thermal Reactor ◽  
The Core ◽  
Experimental Channel ◽  
Paul Scherrer ◽  
The University ◽  
École Polytechnique ◽  
Rate Gradient

Three 1-mm3 miniature fiber-coupled scintillators have been used to perform cm-wise resolution measurements of the thermal neutron flux within experimental channels of the SUR-100 facility, a zero power thermal reactor operated by the Institute of Nuclear Technology and Energy Systems at the University of Stuttgart. The detection system is developed at the École Polytechnique Fédérale de Lausanne in collaboration with the Paul Scherrer Institut. Thermal neutrons count rates were measured along the experimental channels I and II, which cross the reactor at the center and tangentially to the core, respectively. The reactor was modelled with the Monte Carlo neutron transport code Serpent-2.1.31. The comparison of experimental and computed reaction rate distributions showed a good agreement within the core region, with discrepancies within 2σ. An unexpected discrepancy, probably caused by a geometric inconsistency in the computational model of the reactor, was observed in the reflector region of the experimental channel I, where a 20% difference (i.e. 8σ) was found between experimental and simulated results. Significant discrepancies, respectively worth 10σ and 15σ, were noticed at distance, in the lead shielding region, for both experimental channels I and II. In addition, reaction rate gradients across the 2.6 cm and 5.4 cm diameters of both channels were measured. A horizontal reaction rate gradient of (9.09 ± 0.20) % was measured within 2.4 cm across the diameter of the experimental channel II, with a difference from computed results of 2%. The absence of a vertical reaction rate gradient inside the experimental channel I was confirmed by measurements.

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