Author: Sophit Pongpun
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This thesis focuses on designing, building, and analyzing a neutron detection system to measure neutron fluxes of a TRIGA reactor at Texas A&M University to verify newly developed simulation codes. Such a system must be designed to cover a wide range of neutron fluxes in transient power surges (up to 1015 neutrons/cm2/s, lasting 20 to 50 ms) and in steady-state operations (1013 neutrons/cm2/s at full power of one megawatt). The size of the detector is limited to a maximum of 9.525 mm outer diameter including housing. The detection system consisted of slow neutron detectors, associated electronics, data acquisition and storage equipment, and an analysis software. The detector used boron- 10 to capture slow neutrons, generating charged particles within an ionization chamber filled with air. Due to the low Q-value of the reaction, a high gain charge-sensitive preamplifier, which was a part of a miniature 16.9 mm x 298.5 mm electronic package, was placed within 1.7 m of the detector to minimize noise level. The preamplifier was designed to offer pulse mode, current mode, and high voltage current mode of operation. Experimental data were acquired at 20 MHz using a solid-state drive for data storage and were subjected to 250 MHz for up to eight-hour continuous operation using an array of five three-TB hard drives. Data analysis software was programmed using MATLAB. In addition to analysis using the shaping amplifier's output, an algorithm to generate a radiation pulse from the directly digitized preamplifier signal was proposed and tested with test pulses simulating neutron events. The detection system was tested with isotopic sources and in a dry tube located near the TRIGA reactor. The latter showed an increase in the number of gamma events with the reactor power, whereas the number of neutron events was also proportional to the power. In addition, a trial run of in-core measurements was performed. The results suggested that high gamma radiation present in the core interfered with the neutron signal. Suggestions was made for modification of the mechanical assembly of the system, compensation for gamma signals, and additional tests to improve analysis of the neutron signal.
A Neutron Measurement System Design for Pulsed Triga Reactor Experiment at Texas A&M University
Author: Sophit Pongpun
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This thesis focuses on designing, building, and analyzing a neutron detection system to measure neutron fluxes of a TRIGA reactor at Texas A&M University to verify newly developed simulation codes. Such a system must be designed to cover a wide range of neutron fluxes in transient power surges (up to 1015 neutrons/cm2/s, lasting 20 to 50 ms) and in steady-state operations (1013 neutrons/cm2/s at full power of one megawatt). The size of the detector is limited to a maximum of 9.525 mm outer diameter including housing. The detection system consisted of slow neutron detectors, associated electronics, data acquisition and storage equipment, and an analysis software. The detector used boron- 10 to capture slow neutrons, generating charged particles within an ionization chamber filled with air. Due to the low Q-value of the reaction, a high gain charge-sensitive preamplifier, which was a part of a miniature 16.9 mm x 298.5 mm electronic package, was placed within 1.7 m of the detector to minimize noise level. The preamplifier was designed to offer pulse mode, current mode, and high voltage current mode of operation. Experimental data were acquired at 20 MHz using a solid-state drive for data storage and were subjected to 250 MHz for up to eight-hour continuous operation using an array of five three-TB hard drives. Data analysis software was programmed using MATLAB. In addition to analysis using the shaping amplifier's output, an algorithm to generate a radiation pulse from the directly digitized preamplifier signal was proposed and tested with test pulses simulating neutron events. The detection system was tested with isotopic sources and in a dry tube located near the TRIGA reactor. The latter showed an increase in the number of gamma events with the reactor power, whereas the number of neutron events was also proportional to the power. In addition, a trial run of in-core measurements was performed. The results suggested that high gamma radiation present in the core interfered with the neutron signal. Suggestions was made for modification of the mechanical assembly of the system, compensation for gamma signals, and additional tests to improve analysis of the neutron signal.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This thesis focuses on designing, building, and analyzing a neutron detection system to measure neutron fluxes of a TRIGA reactor at Texas A&M University to verify newly developed simulation codes. Such a system must be designed to cover a wide range of neutron fluxes in transient power surges (up to 1015 neutrons/cm2/s, lasting 20 to 50 ms) and in steady-state operations (1013 neutrons/cm2/s at full power of one megawatt). The size of the detector is limited to a maximum of 9.525 mm outer diameter including housing. The detection system consisted of slow neutron detectors, associated electronics, data acquisition and storage equipment, and an analysis software. The detector used boron- 10 to capture slow neutrons, generating charged particles within an ionization chamber filled with air. Due to the low Q-value of the reaction, a high gain charge-sensitive preamplifier, which was a part of a miniature 16.9 mm x 298.5 mm electronic package, was placed within 1.7 m of the detector to minimize noise level. The preamplifier was designed to offer pulse mode, current mode, and high voltage current mode of operation. Experimental data were acquired at 20 MHz using a solid-state drive for data storage and were subjected to 250 MHz for up to eight-hour continuous operation using an array of five three-TB hard drives. Data analysis software was programmed using MATLAB. In addition to analysis using the shaping amplifier's output, an algorithm to generate a radiation pulse from the directly digitized preamplifier signal was proposed and tested with test pulses simulating neutron events. The detection system was tested with isotopic sources and in a dry tube located near the TRIGA reactor. The latter showed an increase in the number of gamma events with the reactor power, whereas the number of neutron events was also proportional to the power. In addition, a trial run of in-core measurements was performed. The results suggested that high gamma radiation present in the core interfered with the neutron signal. Suggestions was made for modification of the mechanical assembly of the system, compensation for gamma signals, and additional tests to improve analysis of the neutron signal.
The Determination of Neutron Flux in the Texas A & M Triga Reactor During Pulse and Steady-state Operations
Author: John Joseph O'Donnell
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 80
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 80
Book Description
Nuclear Science Abstracts
Experimental Neutron Flux Measurements and Power Calibration in the Kansas State University Triga Mark II Nuclear Reactor
Energy Research Abstracts
Nuclear Design Study on Advanced Neutron Measurement System for DT Burn Control in Fusion Experimental Reactor
Neutron Spectrum Measurement with a TRIGA Reactor
Author: Yehoshua Schmuckler
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 154
Book Description
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 154
Book Description
History, Development and Future of TRIGA Research Reactors
Author:
Publisher:
ISBN: 9789201281197
Category : Nuclear reactors
Languages : en
Pages : 131
Book Description
Publisher:
ISBN: 9789201281197
Category : Nuclear reactors
Languages : en
Pages : 131
Book Description
Nuclear Safety
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1204
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1204
Book Description