Using the Time-Correlated Induced Fission Method to Simultaneously Measure the<sup>235</sup>U Content and the Burnable Poison Content in LWR Fuel Assemblies

Root, Margaret A.; Menlove, H.O.; Lanza, R.; Rael, Carlos D.; Miller, Katherine; Marlow, Johnna B; Wendelberger, James G.

doi:10.1080/00295450.2018.1429112

Cited by 4 publications

(2 citation statements)

References 6 publications

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“…Hence, regular replacement of 252 Cf sources may be required for uninterrupted operations. Additionally, should an SF source be used for the active assay of fissile material in terms of counting real coincidences from IF, it may be significant to properly distinguish the contribution of the interrogating source from the response of the interrogated item [55,56]. *The intensities of these isotopic sources scale with the decay of the driving isotope.…”

Section: ) Spontaneous Fission Sourcesmentioning

confidence: 99%

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Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations

Evans¹,

Henzl

Swift

et al. 2021

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Section: ) Spontaneous Fission Sourcesmentioning

confidence: 99%

“…A similar approach could likely be adopted for the assay of 233 U. A similar case can be made for the extension of several other methods developed for the active assay of 235 U, including using 252 Cf [55,56,65] or neutron generator techniques such as differential die-away [65,66].…”

Section: Active Nondestructive Assaymentioning

confidence: 99%

Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations

Evans¹,

Henzl

Swift

et al. 2021

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Principles of Neutron Coincidence Counting

Swinhoe,

Ensslin,

Hutchinson

et al. 2024

Nondestructive Assay of Nuclear Materials for Safeguards and Security

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This chapter describes the principles involved with using neutron coincidences that obtain more information about a measured sample than through singles counting alone. The chapter describes the origin of neutron correlations and how they manifest themselves in the neutron pulse train from a detector. The Rossi-α distribution is presented. The chapter then describes measurement and analysis methods used to extract and analyze correlated counting rates, such as the Feynman variance to mean method and the shift register coincidence circuit. These methods can be used to estimate fission rate and neutron multiplication. Dead time corrections, multiple pulsing and the uncertainties resulting from counting statistics are presented. Several passive methods for the determination of 240Pueffective mass are presented in detail: ‘passive calibration curve’, ‘known alpha’ and ‘known multiplication’. This is followed by a description of active coincidence methods, in which an external neutron source is used to induce fission in the item of interest. This section includes a discussion of the selection of the external source, the use of fast and thermal interrogation modes and a presentation of measurement uncertainties. One example is given of an active technique to measure uranium linear density and burnable poison simultaneously.

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Passive Neutron Instrumentation and Applications

Weinmann-Smith,

Aucott,

Belian

et al. 2024

Nondestructive Assay of Nuclear Materials for Safeguards and Security

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This chapter presents a description of most of the instruments that are currently in use for the measurement of plutonium and uranium using passive methods (without an external source). This includes the acquisition electronics as well as Singles counting methods, coincidence counting methods and multiplicity counting methods. The Singles counting applications include the measurement of waste and curium bearing materials. The coincidence counting applications include bulk plutonium, bulk uranium, waste and holdup measurements and fresh fuel assemblies. The multiplicity application description includes advantages and disadvantages and multiplicity detector design. There is also a description of some non-3He systems. The chapter concludes with a description of additional concepts: neutron imagers, list-mode data analysis, distributed source term analysis, unattended monitoring and MCNP modeling for detector design.

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Using the Time-Correlated Induced Fission Method to Simultaneously Measure the²³⁵U Content and the Burnable Poison Content in LWR Fuel Assemblies

Cited by 4 publications

References 6 publications

Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations

Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations

Principles of Neutron Coincidence Counting

Passive Neutron Instrumentation and Applications

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Using the Time-Correlated Induced Fission Method to Simultaneously Measure the235U Content and the Burnable Poison Content in LWR Fuel Assemblies

Cited by 4 publications

References 6 publications

Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations

Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations

Principles of Neutron Coincidence Counting

Passive Neutron Instrumentation and Applications

Contact Info

Product

Resources

About

Using the Time-Correlated Induced Fission Method to Simultaneously Measure the²³⁵U Content and the Burnable Poison Content in LWR Fuel Assemblies