Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor
The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Ajijul Hoq, M. [verfasserIn] |
|---|
| Format: |
E-Artikel |
|---|---|
| Sprache: |
Englisch |
| Erschienen: |
2017transfer abstract |
|---|
| Schlagwörter: |
|---|
| Umfang: |
5 |
|---|
| Übergeordnetes Werk: |
Enthalten in: Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system - Wang, Lu ELSEVIER, 2018, a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science, Amsterdam [u.a.] |
|---|---|
| Übergeordnetes Werk: |
volume:130 ; year:2017 ; pages:29-33 ; extent:5 |
| Links: |
|---|
| DOI / URN: |
10.1016/j.apradiso.2017.09.001 |
|---|
| Katalog-ID: |
ELV04089150X |
|---|
| LEADER | 01000caa a22002652 4500 | ||
|---|---|---|---|
| 001 | ELV04089150X | ||
| 003 | DE-627 | ||
| 005 | 20230625233133.0 | ||
| 007 | cr uuu---uuuuu | ||
| 008 | 180725s2017 xx |||||o 00| ||eng c | ||
| 024 | 7 | |a 10.1016/j.apradiso.2017.09.001 |2 doi | |
| 028 | 5 | 2 | |a GBV00000000000409.pica |
| 035 | |a (DE-627)ELV04089150X | ||
| 035 | |a (ELSEVIER)S0969-8043(16)30574-7 | ||
| 040 | |a DE-627 |b ger |c DE-627 |e rakwb | ||
| 041 | |a eng | ||
| 082 | 0 | 4 | |a 660 |q VZ |
| 084 | |a 38.51 |2 bkl | ||
| 084 | |a 57.36 |2 bkl | ||
| 100 | 1 | |a Ajijul Hoq, M. |e verfasserin |4 aut | |
| 245 | 1 | 0 | |a Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor |
| 264 | 1 | |c 2017transfer abstract | |
| 300 | |a 5 | ||
| 336 | |a nicht spezifiziert |b zzz |2 rdacontent | ||
| 337 | |a nicht spezifiziert |b z |2 rdamedia | ||
| 338 | |a nicht spezifiziert |b zu |2 rdacarrier | ||
| 520 | |a The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. | ||
| 520 | |a The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. | ||
| 650 | 7 | |a TRIGA Research Reactor |2 Elsevier | |
| 650 | 7 | |a Radiological safety |2 Elsevier | |
| 650 | 7 | |a Cooling mode |2 Elsevier | |
| 650 | 7 | |a Radiation survey meter |2 Elsevier | |
| 650 | 7 | |a Dose rate |2 Elsevier | |
| 700 | 1 | |a Malek Soner, M.A. |4 oth | |
| 700 | 1 | |a Salam, M.A. |4 oth | |
| 700 | 1 | |a Haque, M.M. |4 oth | |
| 700 | 1 | |a Khanom, Salma |4 oth | |
| 700 | 1 | |a Fahad, S.M. |4 oth | |
| 773 | 0 | 8 | |i Enthalten in |n Elsevier Science |a Wang, Lu ELSEVIER |t Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system |d 2018 |d a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science |g Amsterdam [u.a.] |w (DE-627)ELV001919369 |
| 773 | 1 | 8 | |g volume:130 |g year:2017 |g pages:29-33 |g extent:5 |
| 856 | 4 | 0 | |u https://doi.org/10.1016/j.apradiso.2017.09.001 |3 Volltext |
| 912 | |a GBV_USEFLAG_U | ||
| 912 | |a GBV_ELV | ||
| 912 | |a SYSFLAG_U | ||
| 912 | |a SSG-OLC-PHA | ||
| 912 | |a SSG-OPC-GGO | ||
| 936 | b | k | |a 38.51 |j Geologie fossiler Brennstoffe |q VZ |
| 936 | b | k | |a 57.36 |j Erdölgewinnung |j Erdgasgewinnung |q VZ |
| 951 | |a AR | ||
| 952 | |d 130 |j 2017 |h 29-33 |g 5 | ||
| author_variant |
h m a hm hma |
|---|---|
| matchkey_str |
ajijulhoqmmaleksonermasalammahaquemmkhan:2017----:xeietltdordainoeaetifrnsrtgconsfh |
| hierarchy_sort_str |
2017transfer abstract |
| bklnumber |
38.51 57.36 |
| publishDate |
2017 |
| allfields |
10.1016/j.apradiso.2017.09.001 doi GBV00000000000409.pica (DE-627)ELV04089150X (ELSEVIER)S0969-8043(16)30574-7 DE-627 ger DE-627 rakwb eng 660 VZ 38.51 bkl 57.36 bkl Ajijul Hoq, M. verfasserin aut Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor 2017transfer abstract 5 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate Elsevier Malek Soner, M.A. oth Salam, M.A. oth Haque, M.M. oth Khanom, Salma oth Fahad, S.M. oth Enthalten in Elsevier Science Wang, Lu ELSEVIER Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system 2018 a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science Amsterdam [u.a.] (DE-627)ELV001919369 volume:130 year:2017 pages:29-33 extent:5 https://doi.org/10.1016/j.apradiso.2017.09.001 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA SSG-OPC-GGO 38.51 Geologie fossiler Brennstoffe VZ 57.36 Erdölgewinnung Erdgasgewinnung VZ AR 130 2017 29-33 5 |
| spelling |
10.1016/j.apradiso.2017.09.001 doi GBV00000000000409.pica (DE-627)ELV04089150X (ELSEVIER)S0969-8043(16)30574-7 DE-627 ger DE-627 rakwb eng 660 VZ 38.51 bkl 57.36 bkl Ajijul Hoq, M. verfasserin aut Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor 2017transfer abstract 5 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate Elsevier Malek Soner, M.A. oth Salam, M.A. oth Haque, M.M. oth Khanom, Salma oth Fahad, S.M. oth Enthalten in Elsevier Science Wang, Lu ELSEVIER Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system 2018 a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science Amsterdam [u.a.] (DE-627)ELV001919369 volume:130 year:2017 pages:29-33 extent:5 https://doi.org/10.1016/j.apradiso.2017.09.001 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA SSG-OPC-GGO 38.51 Geologie fossiler Brennstoffe VZ 57.36 Erdölgewinnung Erdgasgewinnung VZ AR 130 2017 29-33 5 |
| allfields_unstemmed |
10.1016/j.apradiso.2017.09.001 doi GBV00000000000409.pica (DE-627)ELV04089150X (ELSEVIER)S0969-8043(16)30574-7 DE-627 ger DE-627 rakwb eng 660 VZ 38.51 bkl 57.36 bkl Ajijul Hoq, M. verfasserin aut Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor 2017transfer abstract 5 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate Elsevier Malek Soner, M.A. oth Salam, M.A. oth Haque, M.M. oth Khanom, Salma oth Fahad, S.M. oth Enthalten in Elsevier Science Wang, Lu ELSEVIER Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system 2018 a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science Amsterdam [u.a.] (DE-627)ELV001919369 volume:130 year:2017 pages:29-33 extent:5 https://doi.org/10.1016/j.apradiso.2017.09.001 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA SSG-OPC-GGO 38.51 Geologie fossiler Brennstoffe VZ 57.36 Erdölgewinnung Erdgasgewinnung VZ AR 130 2017 29-33 5 |
| allfieldsGer |
10.1016/j.apradiso.2017.09.001 doi GBV00000000000409.pica (DE-627)ELV04089150X (ELSEVIER)S0969-8043(16)30574-7 DE-627 ger DE-627 rakwb eng 660 VZ 38.51 bkl 57.36 bkl Ajijul Hoq, M. verfasserin aut Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor 2017transfer abstract 5 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate Elsevier Malek Soner, M.A. oth Salam, M.A. oth Haque, M.M. oth Khanom, Salma oth Fahad, S.M. oth Enthalten in Elsevier Science Wang, Lu ELSEVIER Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system 2018 a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science Amsterdam [u.a.] (DE-627)ELV001919369 volume:130 year:2017 pages:29-33 extent:5 https://doi.org/10.1016/j.apradiso.2017.09.001 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA SSG-OPC-GGO 38.51 Geologie fossiler Brennstoffe VZ 57.36 Erdölgewinnung Erdgasgewinnung VZ AR 130 2017 29-33 5 |
| allfieldsSound |
10.1016/j.apradiso.2017.09.001 doi GBV00000000000409.pica (DE-627)ELV04089150X (ELSEVIER)S0969-8043(16)30574-7 DE-627 ger DE-627 rakwb eng 660 VZ 38.51 bkl 57.36 bkl Ajijul Hoq, M. verfasserin aut Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor 2017transfer abstract 5 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate Elsevier Malek Soner, M.A. oth Salam, M.A. oth Haque, M.M. oth Khanom, Salma oth Fahad, S.M. oth Enthalten in Elsevier Science Wang, Lu ELSEVIER Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system 2018 a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science Amsterdam [u.a.] (DE-627)ELV001919369 volume:130 year:2017 pages:29-33 extent:5 https://doi.org/10.1016/j.apradiso.2017.09.001 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA SSG-OPC-GGO 38.51 Geologie fossiler Brennstoffe VZ 57.36 Erdölgewinnung Erdgasgewinnung VZ AR 130 2017 29-33 5 |
| language |
English |
| source |
Enthalten in Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system Amsterdam [u.a.] volume:130 year:2017 pages:29-33 extent:5 |
| sourceStr |
Enthalten in Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system Amsterdam [u.a.] volume:130 year:2017 pages:29-33 extent:5 |
| format_phy_str_mv |
Article |
| bklname |
Geologie fossiler Brennstoffe Erdölgewinnung Erdgasgewinnung |
| institution |
findex.gbv.de |
| topic_facet |
TRIGA Research Reactor Radiological safety Cooling mode Radiation survey meter Dose rate |
| dewey-raw |
660 |
| isfreeaccess_bool |
false |
| container_title |
Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system |
| authorswithroles_txt_mv |
Ajijul Hoq, M. @@aut@@ Malek Soner, M.A. @@oth@@ Salam, M.A. @@oth@@ Haque, M.M. @@oth@@ Khanom, Salma @@oth@@ Fahad, S.M. @@oth@@ |
| publishDateDaySort_date |
2017-01-01T00:00:00Z |
| hierarchy_top_id |
ELV001919369 |
| dewey-sort |
3660 |
| id |
ELV04089150X |
| language_de |
englisch |
| fullrecord |
<?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>01000caa a22002652 4500</leader><controlfield tag="001">ELV04089150X</controlfield><controlfield tag="003">DE-627</controlfield><controlfield tag="005">20230625233133.0</controlfield><controlfield tag="007">cr uuu---uuuuu</controlfield><controlfield tag="008">180725s2017 xx |||||o 00| ||eng c</controlfield><datafield tag="024" ind1="7" ind2=" "><subfield code="a">10.1016/j.apradiso.2017.09.001</subfield><subfield code="2">doi</subfield></datafield><datafield tag="028" ind1="5" ind2="2"><subfield code="a">GBV00000000000409.pica</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-627)ELV04089150X</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(ELSEVIER)S0969-8043(16)30574-7</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">DE-627</subfield><subfield code="b">ger</subfield><subfield code="c">DE-627</subfield><subfield code="e">rakwb</subfield></datafield><datafield tag="041" ind1=" " ind2=" "><subfield code="a">eng</subfield></datafield><datafield tag="082" ind1="0" ind2="4"><subfield code="a">660</subfield><subfield code="q">VZ</subfield></datafield><datafield tag="084" ind1=" " ind2=" "><subfield code="a">38.51</subfield><subfield code="2">bkl</subfield></datafield><datafield tag="084" ind1=" " ind2=" "><subfield code="a">57.36</subfield><subfield code="2">bkl</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">Ajijul Hoq, M.</subfield><subfield code="e">verfasserin</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="c">2017transfer abstract</subfield></datafield><datafield tag="300" ind1=" " ind2=" "><subfield code="a">5</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">nicht spezifiziert</subfield><subfield code="b">zzz</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">nicht spezifiziert</subfield><subfield code="b">z</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">nicht spezifiziert</subfield><subfield code="b">zu</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor.</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor.</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">TRIGA Research Reactor</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Radiological safety</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Cooling mode</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Radiation survey meter</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Dose rate</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Malek Soner, M.A.</subfield><subfield code="4">oth</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Salam, M.A.</subfield><subfield code="4">oth</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Haque, M.M.</subfield><subfield code="4">oth</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Khanom, Salma</subfield><subfield code="4">oth</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Fahad, S.M.</subfield><subfield code="4">oth</subfield></datafield><datafield tag="773" ind1="0" ind2="8"><subfield code="i">Enthalten in</subfield><subfield code="n">Elsevier Science</subfield><subfield code="a">Wang, Lu ELSEVIER</subfield><subfield code="t">Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system</subfield><subfield code="d">2018</subfield><subfield code="d">a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science</subfield><subfield code="g">Amsterdam [u.a.]</subfield><subfield code="w">(DE-627)ELV001919369</subfield></datafield><datafield tag="773" ind1="1" ind2="8"><subfield code="g">volume:130</subfield><subfield code="g">year:2017</subfield><subfield code="g">pages:29-33</subfield><subfield code="g">extent:5</subfield></datafield><datafield tag="856" ind1="4" ind2="0"><subfield code="u">https://doi.org/10.1016/j.apradiso.2017.09.001</subfield><subfield code="3">Volltext</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_USEFLAG_U</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_ELV</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SYSFLAG_U</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SSG-OLC-PHA</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SSG-OPC-GGO</subfield></datafield><datafield tag="936" ind1="b" ind2="k"><subfield code="a">38.51</subfield><subfield code="j">Geologie fossiler Brennstoffe</subfield><subfield code="q">VZ</subfield></datafield><datafield tag="936" ind1="b" ind2="k"><subfield code="a">57.36</subfield><subfield code="j">Erdölgewinnung</subfield><subfield code="j">Erdgasgewinnung</subfield><subfield code="q">VZ</subfield></datafield><datafield tag="951" ind1=" " ind2=" "><subfield code="a">AR</subfield></datafield><datafield tag="952" ind1=" " ind2=" "><subfield code="d">130</subfield><subfield code="j">2017</subfield><subfield code="h">29-33</subfield><subfield code="g">5</subfield></datafield></record></collection>
|
| author |
Ajijul Hoq, M. |
| spellingShingle |
Ajijul Hoq, M. ddc 660 bkl 38.51 bkl 57.36 Elsevier TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor |
| authorStr |
Ajijul Hoq, M. |
| ppnlink_with_tag_str_mv |
@@773@@(DE-627)ELV001919369 |
| format |
electronic Article |
| dewey-ones |
660 - Chemical engineering |
| delete_txt_mv |
keep |
| author_role |
aut |
| collection |
elsevier |
| remote_str |
true |
| illustrated |
Not Illustrated |
| topic_title |
660 VZ 38.51 bkl 57.36 bkl Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate Elsevier |
| topic |
ddc 660 bkl 38.51 bkl 57.36 Elsevier TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate |
| topic_unstemmed |
ddc 660 bkl 38.51 bkl 57.36 Elsevier TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate |
| topic_browse |
ddc 660 bkl 38.51 bkl 57.36 Elsevier TRIGA Research Reactor Elsevier Radiological safety Elsevier Cooling mode Elsevier Radiation survey meter Elsevier Dose rate |
| format_facet |
Elektronische Aufsätze Aufsätze Elektronische Ressource |
| format_main_str_mv |
Text Zeitschrift/Artikel |
| carriertype_str_mv |
zu |
| author2_variant |
s m m sm smm m s ms m h mh s k sk s f sf |
| hierarchy_parent_title |
Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system |
| hierarchy_parent_id |
ELV001919369 |
| dewey-tens |
660 - Chemical engineering |
| hierarchy_top_title |
Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system |
| isfreeaccess_txt |
false |
| familylinks_str_mv |
(DE-627)ELV001919369 |
| title |
Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor |
| ctrlnum |
(DE-627)ELV04089150X (ELSEVIER)S0969-8043(16)30574-7 |
| title_full |
Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor |
| author_sort |
Ajijul Hoq, M. |
| journal |
Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system |
| journalStr |
Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system |
| lang_code |
eng |
| isOA_bool |
false |
| dewey-hundreds |
600 - Technology |
| recordtype |
marc |
| publishDateSort |
2017 |
| contenttype_str_mv |
zzz |
| container_start_page |
29 |
| author_browse |
Ajijul Hoq, M. |
| container_volume |
130 |
| physical |
5 |
| class |
660 VZ 38.51 bkl 57.36 bkl |
| format_se |
Elektronische Aufsätze |
| author-letter |
Ajijul Hoq, M. |
| doi_str_mv |
10.1016/j.apradiso.2017.09.001 |
| dewey-full |
660 |
| title_sort |
experimental study of radiation dose rate at different strategic points of the baec triga research reactor |
| title_auth |
Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor |
| abstract |
The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. |
| abstractGer |
The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. |
| abstract_unstemmed |
The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. |
| collection_details |
GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA SSG-OPC-GGO |
| title_short |
Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor |
| url |
https://doi.org/10.1016/j.apradiso.2017.09.001 |
| remote_bool |
true |
| author2 |
Malek Soner, M.A. Salam, M.A. Haque, M.M. Khanom, Salma Fahad, S.M. |
| author2Str |
Malek Soner, M.A. Salam, M.A. Haque, M.M. Khanom, Salma Fahad, S.M. |
| ppnlink |
ELV001919369 |
| mediatype_str_mv |
z |
| isOA_txt |
false |
| hochschulschrift_bool |
false |
| author2_role |
oth oth oth oth oth |
| doi_str |
10.1016/j.apradiso.2017.09.001 |
| up_date |
2024-07-06T18:40:04.822Z |
| _version_ |
1803856070387433472 |
| fullrecord_marcxml |
<?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>01000caa a22002652 4500</leader><controlfield tag="001">ELV04089150X</controlfield><controlfield tag="003">DE-627</controlfield><controlfield tag="005">20230625233133.0</controlfield><controlfield tag="007">cr uuu---uuuuu</controlfield><controlfield tag="008">180725s2017 xx |||||o 00| ||eng c</controlfield><datafield tag="024" ind1="7" ind2=" "><subfield code="a">10.1016/j.apradiso.2017.09.001</subfield><subfield code="2">doi</subfield></datafield><datafield tag="028" ind1="5" ind2="2"><subfield code="a">GBV00000000000409.pica</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-627)ELV04089150X</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(ELSEVIER)S0969-8043(16)30574-7</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">DE-627</subfield><subfield code="b">ger</subfield><subfield code="c">DE-627</subfield><subfield code="e">rakwb</subfield></datafield><datafield tag="041" ind1=" " ind2=" "><subfield code="a">eng</subfield></datafield><datafield tag="082" ind1="0" ind2="4"><subfield code="a">660</subfield><subfield code="q">VZ</subfield></datafield><datafield tag="084" ind1=" " ind2=" "><subfield code="a">38.51</subfield><subfield code="2">bkl</subfield></datafield><datafield tag="084" ind1=" " ind2=" "><subfield code="a">57.36</subfield><subfield code="2">bkl</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">Ajijul Hoq, M.</subfield><subfield code="e">verfasserin</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="c">2017transfer abstract</subfield></datafield><datafield tag="300" ind1=" " ind2=" "><subfield code="a">5</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">nicht spezifiziert</subfield><subfield code="b">zzz</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">nicht spezifiziert</subfield><subfield code="b">z</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">nicht spezifiziert</subfield><subfield code="b">zu</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor.</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor.</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">TRIGA Research Reactor</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Radiological safety</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Cooling mode</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Radiation survey meter</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Dose rate</subfield><subfield code="2">Elsevier</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Malek Soner, M.A.</subfield><subfield code="4">oth</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Salam, M.A.</subfield><subfield code="4">oth</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Haque, M.M.</subfield><subfield code="4">oth</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Khanom, Salma</subfield><subfield code="4">oth</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Fahad, S.M.</subfield><subfield code="4">oth</subfield></datafield><datafield tag="773" ind1="0" ind2="8"><subfield code="i">Enthalten in</subfield><subfield code="n">Elsevier Science</subfield><subfield code="a">Wang, Lu ELSEVIER</subfield><subfield code="t">Time-dependent shape factors for fractured reservoir simulation: Effect of stress sensitivity in matrix system</subfield><subfield code="d">2018</subfield><subfield code="d">a journal of nuclear and radiation techniques and their applications in the physical, chemical, biological, medical, earth, planetary, environmental and engineering science</subfield><subfield code="g">Amsterdam [u.a.]</subfield><subfield code="w">(DE-627)ELV001919369</subfield></datafield><datafield tag="773" ind1="1" ind2="8"><subfield code="g">volume:130</subfield><subfield code="g">year:2017</subfield><subfield code="g">pages:29-33</subfield><subfield code="g">extent:5</subfield></datafield><datafield tag="856" ind1="4" ind2="0"><subfield code="u">https://doi.org/10.1016/j.apradiso.2017.09.001</subfield><subfield code="3">Volltext</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_USEFLAG_U</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_ELV</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SYSFLAG_U</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SSG-OLC-PHA</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SSG-OPC-GGO</subfield></datafield><datafield tag="936" ind1="b" ind2="k"><subfield code="a">38.51</subfield><subfield code="j">Geologie fossiler Brennstoffe</subfield><subfield code="q">VZ</subfield></datafield><datafield tag="936" ind1="b" ind2="k"><subfield code="a">57.36</subfield><subfield code="j">Erdölgewinnung</subfield><subfield code="j">Erdgasgewinnung</subfield><subfield code="q">VZ</subfield></datafield><datafield tag="951" ind1=" " ind2=" "><subfield code="a">AR</subfield></datafield><datafield tag="952" ind1=" " ind2=" "><subfield code="d">130</subfield><subfield code="j">2017</subfield><subfield code="h">29-33</subfield><subfield code="g">5</subfield></datafield></record></collection>
|
| score |
7.3990707 |