{"title":"Analytic derivation of the multiplicity moments in Active Neutron Coincidence Counting with a non-Poissonian interrogation source","authors":"E.O. Cohen , C. Dubi , R. Yankovich","doi":"10.1016/j.nima.2025.170469","DOIUrl":null,"url":null,"abstract":"<div><div>Active Neutron Multiplicity Counting (ANMC) methods utilize an inversion formula to extract the intensity of a fission source. This is achieved by analyzing the sampled moments of the count distribution, which are generated through the process of inducing fissions in the sample using an external interrogation source. ANMC serves as a powerful tool for quantifying fissile mass e.g., for uranium quantification in mines, fuel fabrication facilities, and reprocessing plants. Typical ANMC methods employ Poissonian interrogation neutron sources, such as AmLi, which emit a single neutron at each source event.</div><div>In this study, we expand upon the conventional formulas used in ANMC inversion to accommodate non-Poissonian interrogation sources. Specifically, we derive analytical expressions for the rates of Singles and Doubles events in ANMC systems. This advancement holds practical significance as it enables the future implementation of ANMC methods utilizing external sources with correlated neutrons, such as AmBe or <sup>252</sup>Cf.</div><div>Aligned with established formulas, the derived formulas in this study adhere to the single-group model and incorporate the influence of fission chains through the widely recognized Bohnel method.</div></div>","PeriodicalId":19359,"journal":{"name":"Nuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment","volume":"1076 ","pages":"Article 170469"},"PeriodicalIF":1.5000,"publicationDate":"2025-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0168900225002700","RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"INSTRUMENTS & INSTRUMENTATION","Score":null,"Total":0}
引用次数: 0
Abstract
Active Neutron Multiplicity Counting (ANMC) methods utilize an inversion formula to extract the intensity of a fission source. This is achieved by analyzing the sampled moments of the count distribution, which are generated through the process of inducing fissions in the sample using an external interrogation source. ANMC serves as a powerful tool for quantifying fissile mass e.g., for uranium quantification in mines, fuel fabrication facilities, and reprocessing plants. Typical ANMC methods employ Poissonian interrogation neutron sources, such as AmLi, which emit a single neutron at each source event.
In this study, we expand upon the conventional formulas used in ANMC inversion to accommodate non-Poissonian interrogation sources. Specifically, we derive analytical expressions for the rates of Singles and Doubles events in ANMC systems. This advancement holds practical significance as it enables the future implementation of ANMC methods utilizing external sources with correlated neutrons, such as AmBe or 252Cf.
Aligned with established formulas, the derived formulas in this study adhere to the single-group model and incorporate the influence of fission chains through the widely recognized Bohnel method.
期刊介绍:
Section A of Nuclear Instruments and Methods in Physics Research publishes papers on design, manufacturing and performance of scientific instruments with an emphasis on large scale facilities. This includes the development of particle accelerators, ion sources, beam transport systems and target arrangements as well as the use of secondary phenomena such as synchrotron radiation and free electron lasers. It also includes all types of instrumentation for the detection and spectrometry of radiations from high energy processes and nuclear decays, as well as instrumentation for experiments at nuclear reactors. Specialized electronics for nuclear and other types of spectrometry as well as computerization of measurements and control systems in this area also find their place in the A section.
Theoretical as well as experimental papers are accepted.