Boron-Lined Multichamber and Conventional Neutron Proportional Counter Tests (open access)

Boron-Lined Multichamber and Conventional Neutron Proportional Counter Tests

Radiation portal monitors used for interdiction of illicit materials at borders include highly sensitive neutron detection systems. The main reason for having neutron detection capability is to detect fission neutrons from plutonium. The currently deployed radiation portal monitors (RPMs) from Ludlum and Science Applications International Corporation (SAIC) use neutron detectors based upon 3He-filled gas proportional counters, which are the most common large neutron detector. There is a declining supply of 3He in the world, and thus, methods to reduce the use of this gas in RPMs with minimal changes to the current system designs and sensitivity to cargo-borne neutrons are being investigated. Four technologies have been identified as being currently commercially available, potential alternative neutron detectors to replace the use of 3He in RPMs. These technologies are: 1) Boron trifluoride (BF3)-filled proportional counters, 2) Boron-lined proportional counters, 3) Lithium-loaded glass fibers, and 4) Coated non-scintillating plastic fibers. In addition, a few other companies have detector technologies that might be competitive in the near term as an alternative technology. Reported here are the results of tests of a boron-lined, multichamber proportional counter manufactured by LND, Inc. Also reported are results obtained with an earlier design of conventional, boron-lined, proportional counters from …
Date: September 7, 2010
Creator: Woodring, Mitchell L.; Ely, James H.; Kouzes, Richard T. & Stromswold, David C.
Object Type: Report
System: The UNT Digital Library
Boron-Lined Multitube Neutron Proportional Counter Test (open access)

Boron-Lined Multitube Neutron Proportional Counter Test

Radiation portal monitors used for interdiction of illicit materials at borders include highly sensitive neutron detection systems. The main reason for having neutron detection capability is to detect fission neutrons from plutonium. The currently deployed radiation portal monitors (RPMs) from Ludlum and Science Applications International Corporation (SAIC) use neutron detectors based upon 3He-filled gas proportional counters, which are the most common large neutron detector. There is a declining supply of 3He in the world, and thus, methods to reduce the use of this gas in RPMs with minimal changes to the current system designs and sensitivity to cargo-borne neutrons are being investigated. Four technologies have been identified as being currently commercially available, potential alternative neutron detectors to replace the use of 3He in RPMs. These technologies are: 1) Boron trifluoride (BF3)-filled proportional counters, 2) Boron-lined proportional counters, 3) Lithium-loaded glass fibers, and 4) Coated non-scintillating plastic fibers. In addition, a few other companies have detector technologies that might be competitive in the near term as an alternative technology. Reported here are the results of tests of a boron-lined, “multitube” proportional counter manufactured by Centronic Ltd. (Surry, U.K. and Houston, TX). This testing measured the required performance for neutron detection efficiency …
Date: September 7, 2010
Creator: Woodring, Mitchell L.; Ely, James H.; Kouzes, Richard T. & Stromswold, David C.
Object Type: Report
System: The UNT Digital Library
RETENTION OF SULFATE IN HIGH LEVEL RADIOACTIVE WASTE GLASS (open access)

RETENTION OF SULFATE IN HIGH LEVEL RADIOACTIVE WASTE GLASS

High level radioactive wastes are being vitrified at the Savannah River Site for long term disposal. Many of the wastes contain sulfate at concentrations that can be difficult to retain in borosilicate glass. This study involves efforts to optimize the composition of a glass frit for combination with the waste to improve sulfate retention while meeting other process and product performance constraints. The fabrication and characterization of several series of simulated waste glasses are described. The experiments are detailed chronologically, to provide insight into part of the engineering studies used in developing frit compositions for an operating high level waste vitrification facility. The results lead to the recommendation of a specific frit composition and a concentration limit for sulfate in the glass for the next batch of sludge to be processed at Savannah River.
Date: September 7, 2010
Creator: Fox, K.
Object Type: Article
System: The UNT Digital Library
SECURITY MODELING FOR MARITIME PORT DEFENSE RESOURCE ALLOCATION (open access)

SECURITY MODELING FOR MARITIME PORT DEFENSE RESOURCE ALLOCATION

Redeployment of existing law enforcement resources and optimal use of geographic terrain are examined for countering the threat of a maritime based small-vessel radiological or nuclear attack. The evaluation was based on modeling conducted by the Savannah River National Laboratory that involved the development of options for defensive resource allocation that can reduce the risk of a maritime based radiological or nuclear threat. A diverse range of potential attack scenarios has been assessed. As a result of identifying vulnerable pathways, effective countermeasures can be deployed using current resources. The modeling involved the use of the Automated Vulnerability Evaluation for Risks of Terrorism (AVERT{reg_sign}) software to conduct computer based simulation modeling. The models provided estimates for the probability of encountering an adversary based on allocated resources including response boats, patrol boats and helicopters over various environmental conditions including day, night, rough seas and various traffic flow rates.
Date: September 7, 2010
Creator: Harris, S. & Dunn, D.
Object Type: Article
System: The UNT Digital Library
Th/U-233 multi-recycle in PWRs. (open access)

Th/U-233 multi-recycle in PWRs.

The use of thorium in current or advanced light water reactors (LWRs) has been of interest in recent years. These interests have been associated with the need to increase nuclear fuel resources and the perceived non-proliferation advantages of the utilization of thorium in the fuel cycle. Various options have been considered for the use of thorium in the LWR fuel cycle including: (1) its use in a once-through fuel cycle to replace non-fissile uranium or to extend fuel burnup due to its attractive fertile material conversion, (2) its use for fissile plutonium burning in limited recycle cores, and (3) its advantage in limiting the transuranic elements to be disposed off in a repository (if only Th/U-233 fuel is used). The possibility for thorium utilization in multirecycle system has also been considered by various researchers, primarily because of the potential for near breeders with Th/U-233 in the thermal energy range. The objective of this project is to evaluate the potential of the Th/U-233 fuel multirecycle in current LWRs, with focus this year on pressurized water reactors (PWRs). In this work, approaches for ensuring a sustainable multirecycle without the need for external source of makeup fissile material have been investigated. The intent …
Date: September 7, 2010
Creator: Yun, D.; Kim, T. K.; Taiwo, T. A. & Division, Nuclear Engineering
Object Type: Report
System: The UNT Digital Library
A Bayesian Approach to Multi-Sensor Track Correlation (open access)

A Bayesian Approach to Multi-Sensor Track Correlation

None
Date: September 7, 2010
Creator: Horsley, M
Object Type: Article
System: The UNT Digital Library
A Parallel, High-Fidelity Radar Model (open access)

A Parallel, High-Fidelity Radar Model

None
Date: September 7, 2010
Creator: Horsley, M & Fasenfest, B
Object Type: Article
System: The UNT Digital Library
Chemical Agent Incident-Response and Recovery Decision Process (open access)

Chemical Agent Incident-Response and Recovery Decision Process

None
Date: September 7, 2010
Creator: Raber, E; Greenwalt, R; Hibbard, W; MacQueen, D; Mancieri, S; Reutter, D et al.
Object Type: Report
System: The UNT Digital Library