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Title: Modeling Passive Fast-Neutron Emission Tomography of Spent Nuclear Fuel

Abstract

For the past year Oak Ridge National Laboratory has been developing a passive fast-neutron emission tomography capability. Like the passive gamma emission tomography capability presently being evaluated by the International Atomic Energy Agency, the goal of this capability is to detect the removal or substitution of individual fuel pins in spent nuclear fuel assemblies for international safeguards applications, such as verifying the integrity of an assembly before transfer to difficult-to-access storage. The present imaging technique is based on neutron emissions originating primarily from curium-244, which is produced predominantly at the end of the exposure cycle. As a result, this technique may be sensitive not only to fuel pins that are removed or substituted subsequent to all irradiation, but also to fuel pins that are substituted and subsequently irradiated. At present, a laboratory prototype imager is under construction. The purpose of the prototype is to demonstrate an imaging capability sufficient to resolve individual fuel pins using commercially available boron straw detectors that can withstand the high gamma ray dose from a typical spent fuel assembly. To achieve both practical measurement durations and sufficient resolution to discern individual pins, the prototype imager employs a novel collimator design where the slits of amore » parallel-slit collimator are rearranged to distribute them around a ring surrounding the target fuel assembly. This presentation will report on simulations to understand the neutron signal-to-noise ratio and gamma dose rate as a function of the collimator design, the neutron detector’s response to gamma rays as a function of dose rate, and image reconstruction challenges associated with this collimator design.« less

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1545240
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: International Workshop on Numerical Modeling of NDA Instrumentation and Methods for Nuclear Safeguards - Luxemburg City, , Luxembourg - 5/16/2018 12:00:00 PM-5/17/2018 12:00:00 PM
Country of Publication:
United States
Language:
English

Citation Formats

Hausladen, Paul, Iyengar, Anagha S., Fabris, Lorenzo, Yang, Jinan, Hu, Jianwei, and Lousteau, Angela L. Modeling Passive Fast-Neutron Emission Tomography of Spent Nuclear Fuel. United States: N. p., 2018. Web.
Hausladen, Paul, Iyengar, Anagha S., Fabris, Lorenzo, Yang, Jinan, Hu, Jianwei, & Lousteau, Angela L. Modeling Passive Fast-Neutron Emission Tomography of Spent Nuclear Fuel. United States.
Hausladen, Paul, Iyengar, Anagha S., Fabris, Lorenzo, Yang, Jinan, Hu, Jianwei, and Lousteau, Angela L. Tue . "Modeling Passive Fast-Neutron Emission Tomography of Spent Nuclear Fuel". United States. https://www.osti.gov/servlets/purl/1545240.
@article{osti_1545240,
title = {Modeling Passive Fast-Neutron Emission Tomography of Spent Nuclear Fuel},
author = {Hausladen, Paul and Iyengar, Anagha S. and Fabris, Lorenzo and Yang, Jinan and Hu, Jianwei and Lousteau, Angela L.},
abstractNote = {For the past year Oak Ridge National Laboratory has been developing a passive fast-neutron emission tomography capability. Like the passive gamma emission tomography capability presently being evaluated by the International Atomic Energy Agency, the goal of this capability is to detect the removal or substitution of individual fuel pins in spent nuclear fuel assemblies for international safeguards applications, such as verifying the integrity of an assembly before transfer to difficult-to-access storage. The present imaging technique is based on neutron emissions originating primarily from curium-244, which is produced predominantly at the end of the exposure cycle. As a result, this technique may be sensitive not only to fuel pins that are removed or substituted subsequent to all irradiation, but also to fuel pins that are substituted and subsequently irradiated. At present, a laboratory prototype imager is under construction. The purpose of the prototype is to demonstrate an imaging capability sufficient to resolve individual fuel pins using commercially available boron straw detectors that can withstand the high gamma ray dose from a typical spent fuel assembly. To achieve both practical measurement durations and sufficient resolution to discern individual pins, the prototype imager employs a novel collimator design where the slits of a parallel-slit collimator are rearranged to distribute them around a ring surrounding the target fuel assembly. This presentation will report on simulations to understand the neutron signal-to-noise ratio and gamma dose rate as a function of the collimator design, the neutron detector’s response to gamma rays as a function of dose rate, and image reconstruction challenges associated with this collimator design.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {5}
}

Conference:
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