The Optimization and Calibration of the AWCC Using 252Cf Interrogation and the Comparison with an AmLi Neutron Source

Menlove, H.O.; Rael, Carlos D.

doi:10.2172/1233242

Cited by 5 publications

(3 citation statements)

References 1 publication

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“…An experimental study has shown that a deuterium-deuterium neutron generator could be used in the AWCC and would match or exceed the precision of an AWCC using AmLi sources [5]. Other work has been investigated using 252 Cf sources as replacement interrogation sources [6]. Both options have the potential to replace AmLi sources but have not been implemented domestically.…”

Section: Measurement Equipment Needed To Meet Impactmentioning

confidence: 99%

The Impact of Increased Requirements for Verification Measurements of Category III and IV Receipts

Bean¹,

Smith²

2022

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As part of the regular nuclear material accounting and control process, sites that possess accountable nuclear material are expected to regularly perform measurements of the material. The expectation for the type of measurements and their frequency is set out in US Department of Energy (DOE) Order 474.2, and further detailed in each site's respective material control and accountability (MC&A) plan and associated controlling documents. The measurements of interest in this report are those performed on external (i.e., between DOE sites) transfer receipts of Category III or Category IV accountable materials. In 2020, a revision of DOE Order 474.2 was proposed that would significantly increase the requirement that measurements be performed upon receipt of material, and that those measurements be quantitative verification (rather than qualitative confirmatory) measurements. A survey was performed of DOE sites to discuss the impact on their MC&A measurements program if more rigorous verification measurements requirements for Category III and IV receipts were implemented. An assessment of nondestructive assay (NDA) measurement instruments to meet those needs was also performed. Sites across the board indicated that personnel and budget would have the greatest effect. Sites qualified as Category I and Category II indicated a reduced impact because these sites already have the measurement capabilities and some personnel but would require additional measurement systems. Category III and Category IV sites indicated a much larger impact because these sites generally have smaller MC&A programs. Some smaller sites stated that a measurement program would need to be created to handle the demand. Calorimetry, quantitative gamma spectroscopy, and neutron coincidence counting systems were identified as common systems that could meet the verification measurement requirements. Additionally, calibration standards for the calorimetry and neutron coincidence counting systems are also needed. A comparative study should be performed for the In-Situ Object Counting System (ISOCS) and ISOTOPICS, along with performing a qualification of a commercial-off-the-shelf (COTS) calorimetry system, and development of an active well coincidence counter (AWCC) system that uses a neutron generator.

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Section: Measurement Equipment Needed To Meet Impactmentioning

confidence: 99%

The Impact of Increased Requirements for Verification Measurements of Category III and IV Receipts

Bean¹,

Smith²

2022

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“…Even though the coupling probabilities between the three regions are very low, in average, the measurements result with 252 Cf is expected to show significant increase in the doubles rate compared the doubles rate when AmLi source is used. [18]…”

Section: Detetor Deadtime Modelsmentioning

confidence: 99%

“…The multiplicity ( in 252 Cf is 3.76and multiplicity in IF is 2.44, therefore the combined multiplicity is much higher when 252 Cf is used compared to the combined multiplicity with AmLi (α,n) source. When an effective multiplicity increases, the coincidence rates such as doubles increase as well [18].…”

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confidence: 99%

Comparison Of <sup>252</sup>Cf Time Correlated Induced Fisssion With AmLi Induced Fission On Fresh MTR Research Reactor Fuel

Joshi¹

2017

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The effective application of international safeguards to research reactors requires verification of spent fuel as well as fresh fuel. To accomplish this goal various nondestructive and destructive assay techniques have been developed in the US and around the world. The Advanced Experimental Fuel Counter (AEFC) is a nondestructive assay (NDA) system developed at Los Alamos National Laboratory (LANL) combining both neutron and gamma measurement capabilities. Since spent fuel assemblies are stored in water, the system was designed to be watertight to facilitate underwater measurements by inspectors. The AEFC is comprised of six 3 He detectors as well as a shielded and collimated ion chamber. The 3 He detectors are used for active and passive neutron coincidence counting while the ion chamber is used for gross gamma counting. Active coincidence measurement data is used to measure residual fissile mass, whereas the passive coincidence measurement data along with passive gamma measurement can provide information about burnup, cooling time, and initial enrichment. In the past, most of the active interrogation systems along with the AEFC used an AmLi neutron interrogation source. Owing to the difficulty in obtaining an AmLi source, a 252 Cf spontaneous fission (SF) source was used during a 2014 field trail in Uzbekistan as an alternative. In this study, experiments were performed to calibrate the AEFC instrument and compare use of the 252 Cf spontaneous fission source and the AmLi (α,n) neutron emission source. The 252 Cf source spontaneously emits bursts of time-correlated prompt fission neutrons that thermalize in the water and induce fission in the fuel assembly. The induced fission (IF) neutrons are also time correlated resulting in more correlated neutron detections inside the 3 He detector, which helps reduce the statistical errors in doubles when using the 252 Cf interrogation source instead of the AmLi source. In this work, two MTR fuel assemblies varying both in size and number of fuel plates were measured using 252 Cf and AmLi active interrogation sources. This paper analyzes time correlated induced fission (TCIF) from fresh MTR fuel assemblies due to 252 Cf and AmLi active interrogation sources.

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A comparison of Monte Carlo fission models for safeguards neutron coincidence counters

Weinmann-Smith

Swinhoe

Trahan

et al. 2018

Nuclear Instruments and Methods in Physics Research Section A:

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The Optimization and Calibration of the AWCC Using 252Cf Interrogation and the Comparison with an AmLi Neutron Source

Cited by 5 publications

References 1 publication

The Impact of Increased Requirements for Verification Measurements of Category III and IV Receipts

The Impact of Increased Requirements for Verification Measurements of Category III and IV Receipts

Comparison Of <sup>252</sup>Cf Time Correlated Induced Fisssion With AmLi Induced Fission On Fresh MTR Research Reactor Fuel

A comparison of Monte Carlo fission models for safeguards neutron coincidence counters

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