Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system

Margulis, Marat; Gilad, Erez

doi:10.1016/j.pnucene.2015.12.008

Cited by 8 publications

(3 citation statements)

References 25 publications

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“…In this section, a standard plate-type fuel assembly was calculated. The geometry and compositions of materials are from the MTR benchmark problem (IAEA, 1980;Margulis and Gilad, 2016), given in Figure 9; Table 5. There are 23 fuel…”

Section: Mtr Plate-type Fuel Assemblymentioning

confidence: 99%

Pin-resolved ultra-fine-group with correction method and its application to plate-type fuel reactor analysis

Rao

Peng

et al. 2023

Front. Energy Res.

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In order to perform the resonance calculation efficiently and accurately, several pin-resolved ultra-fine-group methods combining the ultra-fine-group method and Dancoff factor have been developed recently. The ultra-fine-group method is used to consider the self-shielding effect accurately in the 1-D fuel model, and the Dancoff factor is used to consider the shadowing effect in a lattice system. The pin-resolved ultra-fine-group with correction method, combining the ultra-fine-group method and Dancoff factor, is implemented in a transport code using the method of characteristic. In order to expand the application range, the pin-resolved method is extended for the plate-type fuel. Numerical results show good accuracy for the plate-type fuel reactor analysis.

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Section: Mtr Plate-type Fuel Assemblymentioning

confidence: 99%

Pin-resolved ultra-fine-group with correction method and its application to plate-type fuel reactor analysis

Rao

Peng

et al. 2023

Front. Energy Res.

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“…The dimensions of the absorber blades are shown in Figure 3 and were taken from [15] (p. 17) and [16]. The core configuration for Beginning of Life (BOL) is shown in Figure 4 and the atomic density of HEU is taken from [17]. The dimensions of the absorber blades are shown in Figure 3 and were taken from [15] (p. 17) and [16].…”

Section: Benchmark Problemmentioning

confidence: 99%

High-Fidelity Steady-State and Transient Simulations of an MTR Research Reactor Using Serpent2/Subchanflow

2022

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In order to join efforts to develop high-fidelity multi-physics tools for research reactor analysis, the KIT is conducting studies to modify the coupled multi-physics codes developed for power reactors. The coupled system uses the Monte Carlo Serpent 2 code for neutron analysis and the Subchanflow code for thermo-hydraulic analysis. Serpent treats temperature dependence using the target motion sampling method and Subchanflow was previously extended and validated with experimental data for plate-type reactor analysis. This work present for the first time the steady-state and transient neutron and thermo-hydraulic analysis of an MTR core defined in the IAEA 10 MW benchmark using Serpent2/Subchanflow. Important global and local parameters for nominal steady-state conditions were obtained, e.g., the lowest and highest core plate/channel power/temperature, the radial and axial core power profile at the plate level, and the core coolant temperature distribution at the subchannel level. The capabilities of serpent2/Subchanflow to perform transient analysis with on-the-fly motion of the control plates were tested, namely with fast and slow reactivity insertion. Based on the unique results obtained for the first time at the subchannel and plate level, it can be stated that the coupled Serpent2/Subchanflow code is a very promising tool for research reactor safety-related investigations.

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“…Therefore, the research on the fuel burn-up is very important to be done for not only to RSG-GAS core, but also another types of reactor, namely power reactor and another research reactor. Several studies related to the fuel burn-up, include -Simulation of burnup calculation at power plant [2][3][4][5] -Analysis to the fuel burnup of the MTR type research reactor [6,7] -Analysis of measurements data of the RSG-GAS research reactor [8][9][10][11] In the RSG-GAS core in-core fuel management, calculations using computer programs are performed to determine the discharge burn-up in each operating cycle. The computer program as a calculation tool for RSG-GAS core fuel burn-up has been replaced with BATAN-FUEL, previously using the computer program of IAFUEL [12].…”

Section: Introductionmentioning

confidence: 99%

Verification to the RSG-Gas Fuel Discharge Burn-Up Using Srac2006 Module of Corebn/Hist

Susilo

Sembiring

imron³

et al. 2018

Tri Dasa Mega

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VERIFICATION TO THE RSG-GAS FUEL DISCHARGE BURN-UP USING SRAC2006MODULE OF COREBN/HIST. For 30 years operation, some of the modifications to the RSG GAS core has been done, that are changes included the type of fuel from U3O8-Al to U3Si2-Al with the same density 2.96 gU/cc, the loading pattern of standard fuel elements/fuel control elements from 6/1 & 6/2 to 5/1 pattern, and in core fuel management calculation tool has been change from IAFUEL to BATAN-FUEL. To obtain an extension of the operating license for the next 10 years, the RSG-GAS Periodic Safety Assessment Document is need to prepared. According to the Regulatory Body Chairman Regulation No. 2 2015, RSG-GAS safety assessment should be done independently. As part of this assessment the fuel discharge burn-up must be estimated. In this research, to ensure that the misposition of fuel element in the core has not occurred, the investigation to the document operating report related the fuel placement has been done. Therefore, by using 78th to 93rd operation data, verify of the fuel discharge burn-up of the RSG-GAS has been performed by using SRAC2006 module of COREBN/HIST. In addition, the results of these calculations are also made comparative with the operating report data that is calculated by using BATAN-FUEL. Maximum fuel discharge burn-up (57.73% of U-235) was verified still under permissible value determined by the regulatory body (<60% of U-235). Maximum differences value between two computer codes was about 2.12 % of U-235 (3.80%) that is fuel at the B-7 position. Fuel discharge burn-up of RSG-GAS showed almost the same value for each the operation cycle, range of 1.52% of U-235. So it can be concluded that the RSG-GAS core operation over the last ten years was in good fuel management performance, in accordance with the design. BATAN-FUEL has been comformed well enough with COREBN/HIST. Keywords: Discharge Burn-Up, RSG-GAS, COREBN/HIST, BATAN-FUEL ABSTRAK VERIFIKASI TERHADAP BURN-UP BUANG BAHAN BAKAR TERAS RSG-GAS MENGGUNAKAN SRAC2006 MODUL COREBN/HIST. Selama 30 tahun beroperasi, RSG-GAS telah mengalami perubahan modifikasi antara lain jenis bahan bakar dari U3O8-Al menjadi

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Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system

Cited by 8 publications

References 25 publications

Pin-resolved ultra-fine-group with correction method and its application to plate-type fuel reactor analysis

Pin-resolved ultra-fine-group with correction method and its application to plate-type fuel reactor analysis

High-Fidelity Steady-State and Transient Simulations of an MTR Research Reactor Using Serpent2/Subchanflow

Verification to the RSG-Gas Fuel Discharge Burn-Up Using Srac2006 Module of Corebn/Hist

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