1
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Experimental and analytical natural circulation analysis of the Jordanian 5 MW research reactor using plate type fuel by RELAP5 MOD3.3. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109233] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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2
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Zhang D, Ran X, Zhang Y, Zhang H. Study of cooling strategy for pressure vessel in pool research reactor at accident situation. KERNTECHNIK 2021. [DOI: 10.3139/124.190038] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
Pressure vessel in pool layout is usually used in high power and middle pressure research reactor, Flow inversion and residual heat removal is important problem. The heat removal strategy at accident situation for a pressure vessel in pool layout research reactor was studied in the paper, many cases was researched for the ability of heat removal and safety of core.
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3
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MNSR transient analysis using the RELAP5/Mod3.2 code. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2020.03.006] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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4
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Gaikwad AJ, Maheshwari NK, Obaidurrahman K, Gupta A, Pradhan SK. Optimal Main Heat Transport system configuration for a nuclear power plant. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110474] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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5
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Khodadadi H, Ayoobian N. Conceptual design and uncertainty analysis of a typical 50 kW aqueous homogeneous reactor aimed for medical isotope production. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2019.103233] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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6
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Chatzidakis S, Ikonomopoulos A, Alamaniotis M. An Algorithmic Approach for RELAP5/MOD3 Reactivity Insertion Analysis in Research Reactors. NUCL TECHNOL 2017. [DOI: 10.13182/nt12-a14171] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- S. Chatzidakis
- Institute of Nuclear Technology and Radiation Protection, National Center for Scientific Research “Demokritos,” 15310, Aghia Paraskevi, Athens, Greece
| | - A. Ikonomopoulos
- Institute of Nuclear Technology and Radiation Protection, National Center for Scientific Research “Demokritos,” 15310, Aghia Paraskevi, Athens, Greece
| | - M. Alamaniotis
- Purdue University, School of Nuclear Engineering, West Lafayette, Indiana 47907
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7
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Margulis M, Gilad E. Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2015.12.008] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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8
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Zarifi E, Tashakor S, Khorsandi J. Steady state and transient analyses of MNSR reactor using RELAP5 code. KERNTECHNIK 2016. [DOI: 10.3139/124.110560] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
Developing a reliable thermal-hydraulic model of a nuclear reactor is an essential process in the steady state and transient analyses. This paper provides the results of best estimate calculation carried out with reference to Iranian Miniature Neutron Source Reactor (MNSR) using the RELAP5 code. Applying the qualified nodalization and the cross-flow effects are some of the advantages in the present model. Here, various transients including step and ramp reactivity insertions were inspected for safety analysis. The obtained results from the code showed a reasonable agreement with the MNSR Safety Analysis Report (SAR) and existing experimental and reference data.
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Affiliation(s)
- E. Zarifi
- Reactor Research School , Nuclear Science and Technology Research Institute (NSTRI), 14155-1339, Tehran , Iran
| | - S. Tashakor
- Department of Nuclear Engineering , Shiraz Branch, Islamic Azad University, Shiraz , Iran
- Reactor Research School , Nuclear Science and Technology Research Institute (NSTRI), 14155-1339, Tehran , Iran
| | - J. Khorsandi
- Reactors Research School , Nuclear Science and Technology Research Institute (NSTRI), 81465/1589, Esfahan , Iran
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9
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El-Sahlamy N, Khedr A, D’Auria F. Thermal hydraulic analysis of reactivity accidents in MTR research reactors using RELAP5. KERNTECHNIK 2015. [DOI: 10.3139/124.110556] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
The present paper comes in the line with the international approach which use the best estimate codes, instead of conservative codes, to get more realistic prediction of system behavior under off-normal reactor conditions. The aim of the current work is to apply this approach using the thermal-hydraulic system code RELAP5/Mod3.3 in a reassessment of safety of the IAEA benchmark 10 MW Research Reactor. The assessment is performed for both slow and fast reactivity insertion transients at initial power of 1.0 W. The reactor power is calculated using the RELA5 point kinetic model. The reactivity feedback terms are considered in two steps. In the first step the feedback from changes in water density and fuel temperature (Doppler effects) are considered. In the second step the feedback from the water temperature changes is added. The results from the first step are compared with that published in IAEA-TECDOC-643 benchmarks. The comparison shows that RELAP5 over predicts the peak power and consequently the fuel, clad and coolant temperatures in case of fast reactivity insertion. The results from the second step show unjustified values for reactor power. Therefore, the model of reactivity feedback from water temperature changes in the RELAP5 code may have to be reviewed.
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Affiliation(s)
- N. El-Sahlamy
- Nuclear and Radiological Regulatory Authority , Cairo , Egypt
| | - A. Khedr
- Nuclear and Radiological Regulatory Authority , Cairo , Egypt
| | - F. D’Auria
- Facolta di Ingegneria , Universita di Pisa, Via Diotisalvi, 2 – 56126, Pisa , Italy
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A comparative assessment of independent thermal-hydraulic models for research reactors: The RSG-GAS case. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2013.11.076] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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11
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Comparative safety assessment of HEU and LEU core of MNSR under large reactivity insertion accidents. ANN NUCL ENERGY 2014. [DOI: 10.1016/j.anucene.2013.08.034] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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12
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Chatzidakis S, Ikonomopoulos A. Phenomenological investigation of loss of coolant accident in a research reactor facility. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2012.08.025] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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13
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Evaluation of RELAP5/MOD3 behavior against loss of flow experimental results from two research reactor facilities. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2012.11.005] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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14
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Thermal hydraulic and safety analysis for core conversion (HEU–LEU) of Syrian Miniature Neutron Source Reactor. PROGRESS IN NUCLEAR ENERGY 2012. [DOI: 10.1016/j.pnucene.2012.05.007] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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15
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Feedback reactivity coefficients for the Syrian MNSR research reactor. PROGRESS IN NUCLEAR ENERGY 2012. [DOI: 10.1016/j.pnucene.2011.07.001] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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16
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Thermal-hydraulic and safety aspects of UO2 fuel for low-power reactors. PROGRESS IN NUCLEAR ENERGY 2011. [DOI: 10.1016/j.pnucene.2011.01.004] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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17
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Hamidouche T, Si-Ahmed EK. Analysis of loss of coolant accident in MTR pool type research reactor. PROGRESS IN NUCLEAR ENERGY 2011. [DOI: 10.1016/j.pnucene.2010.12.005] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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