Search engine for discovering works of Art, research articles, and books related to Art and Culture
ShareThis
Javascript must be enabled to continue!

Development of neutron survey meter using prescila neutron probe

View through CrossRef
This paper presents the design and validation of a neutron survey meter. The meter consists of a PRESCILA neutron probe (with good sensitivity, directional response, gamma rejection, and enhanced high-energy response to 20 MeV) and an electrometer developed at Non-Destructive Evaluation center. The homogeneity response of the PRESCILA neutron probe was investigated as a function of distances from the 241Am - 9Be source in order to obtain the appropriate distance for accurate count-rate measurements using the neutron survey meter. A system consists of the PRESCILA neutron probe and the Ludlum Model 2326 electrometer was then used for measuring neutron ambient dose equivalent rates in the range from 50 cm to 200 cm with the step of 25 cm. The relationship between the count-rates and neutron dose equivalent rates (in the distance ranged from 50 to 200 cm) were deduced to validate the proper operation of the neutron survey meter.
Title: Development of neutron survey meter using prescila neutron probe
Description:
This paper presents the design and validation of a neutron survey meter.
The meter consists of a PRESCILA neutron probe (with good sensitivity, directional response, gamma rejection, and enhanced high-energy response to 20 MeV) and an electrometer developed at Non-Destructive Evaluation center.
The homogeneity response of the PRESCILA neutron probe was investigated as a function of distances from the 241Am - 9Be source in order to obtain the appropriate distance for accurate count-rate measurements using the neutron survey meter.
A system consists of the PRESCILA neutron probe and the Ludlum Model 2326 electrometer was then used for measuring neutron ambient dose equivalent rates in the range from 50 cm to 200 cm with the step of 25 cm.
The relationship between the count-rates and neutron dose equivalent rates (in the distance ranged from 50 to 200 cm) were deduced to validate the proper operation of the neutron survey meter.

Related Results

A Method for Determining the Porosity of Pulsed Neutron by Combining Gamma Energy and Time Spectrum
A Method for Determining the Porosity of Pulsed Neutron by Combining Gamma Energy and Time Spectrum
Pulsed-neutron gamma energy spectroscopy and neutron lifetime measurement systems enable the evaluation of the elemental content, saturation. And recent studies have demonstrated t...
Study of coded source neutron imaging based on a compact accelerator
Study of coded source neutron imaging based on a compact accelerator
Compact accelerator based neutron source has lower cost and better flexibility than nuclear reactor. Neutron imaging using such a neutron source has attracted more and more attenti...
Determination of Coal Ash Content by Neutron-Neutron Logging
Determination of Coal Ash Content by Neutron-Neutron Logging
Abstract The research is aimed at assessing the possibility of studying the ash content of coal seams using neutron-neutron logging in coal exploration wells drilled...
A New Method of Porosity Determination by D-T Neutron Generator and Dual CLYC Detector
A New Method of Porosity Determination by D-T Neutron Generator and Dual CLYC Detector
Porosity is one of the essential parameters in conventional oil and gas reservoir evaluation, as well as plays an important role in the calculation of formation saturation and rese...
A Novel Gamma-Thermal Neutron Evaluating Gas Saturation Method Using Pulsed Neutron Logging Tool With Dual-CLYC
A Novel Gamma-Thermal Neutron Evaluating Gas Saturation Method Using Pulsed Neutron Logging Tool With Dual-CLYC
In our previous research which has published in 62th SPWLA symposium, a numerical simulation method was proposed which about the double particle detector CLYC (Cs2LiYCl6:CE) to get...
Neutron and Photon Dose Rates in a D-T Neutron Generator Facility: MCNP Simulations and Experiments
Neutron and Photon Dose Rates in a D-T Neutron Generator Facility: MCNP Simulations and Experiments
Abstract The deuterium-tritium neutron generator is a common neutron source for fast neutron activation analysis. The 14.1 MeV neutrons emitted from a deuterium-tritium n...
Environmental Surveillance Protocols for Highly Pathogenic Avian Influenza (HPAI) v2
Environmental Surveillance Protocols for Highly Pathogenic Avian Influenza (HPAI) v2
EnvironmentalSurveillance Protocols for Highly Pathogenic Avian Influenza (HPAI) This comprehensive protocol suite enables systematic environmental surveillance for avian influenza...

Back to Top