Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor
Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power def...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Salam, M.A. [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2014transfer abstract |
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| Schlagwörter: |
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| Umfang: |
6 |
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| Übergeordnetes Werk: |
Enthalten in: Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts - Meyers, Carina Mello Guimaraes ELSEVIER, 2022, the international review journal covering all aspects of nuclear energy, Amsterdam [u.a.] |
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| Übergeordnetes Werk: |
volume:74 ; year:2014 ; pages:160-165 ; extent:6 |
| Links: |
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| DOI / URN: |
10.1016/j.pnucene.2014.02.025 |
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ELV033694788 |
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| 520 | |a Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. | ||
| 520 | |a Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. | ||
| 650 | 7 | |a TRIGA research reactor |2 Elsevier | |
| 650 | 7 | |a Temperature coefficient of reactivity |2 Elsevier | |
| 650 | 7 | |a Xenon poisoning |2 Elsevier | |
| 650 | 7 | |a Coefficient of reactivity |2 Elsevier | |
| 650 | 7 | |a Excess reactivity |2 Elsevier | |
| 700 | 1 | |a Soner, M.A.M. |4 oth | |
| 700 | 1 | |a Sarder, M.A. |4 oth | |
| 700 | 1 | |a Haque, A. |4 oth | |
| 700 | 1 | |a Uddin, M.M. |4 oth | |
| 700 | 1 | |a Rahman, A. |4 oth | |
| 700 | 1 | |a Rahman, M.M. |4 oth | |
| 700 | 1 | |a Sarkar, M.M. |4 oth | |
| 700 | 1 | |a Islam, S.M.A. |4 oth | |
| 773 | 0 | 8 | |i Enthalten in |n Elsevier Science |a Meyers, Carina Mello Guimaraes ELSEVIER |t Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts |d 2022 |d the international review journal covering all aspects of nuclear energy |g Amsterdam [u.a.] |w (DE-627)ELV007755775 |
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10.1016/j.pnucene.2014.02.025 doi GBVA2014004000003.pica (DE-627)ELV033694788 (ELSEVIER)S0149-1970(14)00063-8 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Salam, M.A. verfasserin aut Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor 2014transfer abstract 6 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. TRIGA research reactor Elsevier Temperature coefficient of reactivity Elsevier Xenon poisoning Elsevier Coefficient of reactivity Elsevier Excess reactivity Elsevier Soner, M.A.M. oth Sarder, M.A. oth Haque, A. oth Uddin, M.M. oth Rahman, A. oth Rahman, M.M. oth Sarkar, M.M. oth Islam, S.M.A. oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:74 year:2014 pages:160-165 extent:6 https://doi.org/10.1016/j.pnucene.2014.02.025 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 74 2014 160-165 6 045F 620 |
| spelling |
10.1016/j.pnucene.2014.02.025 doi GBVA2014004000003.pica (DE-627)ELV033694788 (ELSEVIER)S0149-1970(14)00063-8 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Salam, M.A. verfasserin aut Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor 2014transfer abstract 6 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. TRIGA research reactor Elsevier Temperature coefficient of reactivity Elsevier Xenon poisoning Elsevier Coefficient of reactivity Elsevier Excess reactivity Elsevier Soner, M.A.M. oth Sarder, M.A. oth Haque, A. oth Uddin, M.M. oth Rahman, A. oth Rahman, M.M. oth Sarkar, M.M. oth Islam, S.M.A. oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:74 year:2014 pages:160-165 extent:6 https://doi.org/10.1016/j.pnucene.2014.02.025 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 74 2014 160-165 6 045F 620 |
| allfields_unstemmed |
10.1016/j.pnucene.2014.02.025 doi GBVA2014004000003.pica (DE-627)ELV033694788 (ELSEVIER)S0149-1970(14)00063-8 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Salam, M.A. verfasserin aut Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor 2014transfer abstract 6 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. TRIGA research reactor Elsevier Temperature coefficient of reactivity Elsevier Xenon poisoning Elsevier Coefficient of reactivity Elsevier Excess reactivity Elsevier Soner, M.A.M. oth Sarder, M.A. oth Haque, A. oth Uddin, M.M. oth Rahman, A. oth Rahman, M.M. oth Sarkar, M.M. oth Islam, S.M.A. oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:74 year:2014 pages:160-165 extent:6 https://doi.org/10.1016/j.pnucene.2014.02.025 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 74 2014 160-165 6 045F 620 |
| allfieldsGer |
10.1016/j.pnucene.2014.02.025 doi GBVA2014004000003.pica (DE-627)ELV033694788 (ELSEVIER)S0149-1970(14)00063-8 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Salam, M.A. verfasserin aut Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor 2014transfer abstract 6 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. TRIGA research reactor Elsevier Temperature coefficient of reactivity Elsevier Xenon poisoning Elsevier Coefficient of reactivity Elsevier Excess reactivity Elsevier Soner, M.A.M. oth Sarder, M.A. oth Haque, A. oth Uddin, M.M. oth Rahman, A. oth Rahman, M.M. oth Sarkar, M.M. oth Islam, S.M.A. oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:74 year:2014 pages:160-165 extent:6 https://doi.org/10.1016/j.pnucene.2014.02.025 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 74 2014 160-165 6 045F 620 |
| allfieldsSound |
10.1016/j.pnucene.2014.02.025 doi GBVA2014004000003.pica (DE-627)ELV033694788 (ELSEVIER)S0149-1970(14)00063-8 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Salam, M.A. verfasserin aut Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor 2014transfer abstract 6 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. TRIGA research reactor Elsevier Temperature coefficient of reactivity Elsevier Xenon poisoning Elsevier Coefficient of reactivity Elsevier Excess reactivity Elsevier Soner, M.A.M. oth Sarder, M.A. oth Haque, A. oth Uddin, M.M. oth Rahman, A. oth Rahman, M.M. oth Sarkar, M.M. oth Islam, S.M.A. oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:74 year:2014 pages:160-165 extent:6 https://doi.org/10.1016/j.pnucene.2014.02.025 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 74 2014 160-165 6 045F 620 |
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Enthalten in Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts Amsterdam [u.a.] volume:74 year:2014 pages:160-165 extent:6 |
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Enthalten in Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts Amsterdam [u.a.] volume:74 year:2014 pages:160-165 extent:6 |
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Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts |
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Salam, M.A. @@aut@@ Soner, M.A.M. @@oth@@ Sarder, M.A. @@oth@@ Haque, A. @@oth@@ Uddin, M.M. @@oth@@ Rahman, A. @@oth@@ Rahman, M.M. @@oth@@ Sarkar, M.M. @@oth@@ Islam, S.M.A. @@oth@@ |
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Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor |
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Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. |
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Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. |
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Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor. |
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