Results of the Swedish spent fuel measurement field trials with the Differential Die-Away Self-Interrogation Instrument

Trahan, Alexis; McMath, Garrett Earl; Mendoza, Paul Michael; Trellue, Holly R.; Bäckström, Ulrika; Balkeståhl, L. Caldeira; Grape, Sophie; Henzl, Vlad; Leyba, Daniel; Root, Margaret A.; Sjöland, Anders

doi:10.1016/j.nima.2019.163329

Cited by 6 publications

(2 citation statements)

References 8 publications

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“…However, the so-called SKB-50 fuel, https://doi.org/10.1016/j.anucene.2023.109941 Received 26 January 2023; Received in revised form 15 April 2023; Accepted 21 May 2023 selected in 2013-2014, comprising 25 BWR and25 PWR SNFs from the Swedish nuclear reactors, is spanning the range of fuel parameters initial enrichment, burnup, cooling time expected to be encountered during encapsulation and geological storage. It constitutes a unique set of SNFs that have been repeatedly measured by multiple instruments over many years (Jansson et al, 2020;Vaccaro et al, 2016;Trahan et al, 2020), to develop techniques to be used for SNFs characterization before encapsulation and final storage. The collected data also offers a unique opportunity to evaluate the reproducibility of gamma spectroscopy of SNF.…”

Section: Introductionmentioning

confidence: 99%

Spent Nuclear Fuel Passive Gamma Analysis And Reproducibility: Application to Skb-50 Assemblies

Solans

Sjöstrand

Jansson

et al. 2023

Preprint

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Section: Introductionmentioning

confidence: 99%

Spent Nuclear Fuel Passive Gamma Analysis And Reproducibility: Application to Skb-50 Assemblies

Solans

Sjöstrand

Jansson

et al. 2023

Preprint

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“…Among these parameters, the sub-critical neutron multiplicity of the spent fuel bundle is of particular importance. One method for measuring this observable is via coincidental detection of pairs of neutrons emitted from decays within the spent fuel [4,5]. Due to the necessary proximity to the fuel assembly, this technique puts requirements on the employed detector systems.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of the in-situ Performance of Neutron Detectors based on EJ-426 Scintillator Screens for Spent Fuel Characterization

Perrey,

Ros,

Elfman

et al. 2021

Preprint

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The reliable detection of neutrons in a harsh gamma-ray environment is an important aspect of establishing non-destructive methods for the characterization of spent nuclear fuel. In this study, we present results from extended in-situ monitoring of detector systems consisting of commercially available components: EJ-426, a 6 Li-enriched solid-state scintillator material sensitive to thermal neutrons, and two different types of Hamamatsu photomultiplier tubes (PMT). Over the period of eight months, these detectors were operated in close vicinity to spent nuclear fuel stored at the interim storage facility CLAB, Oskarshamn, Sweden. At the measurement position the detectors were continuously exposed to an estimated (moderated) neutron flux of approx. 280 n/s cm 2 and a gammaray dose rate of approximately 6 Sv/h.A trigger-less data acquisition system has been developed that autonomously records full waveforms of the detector signals at regular intervals. Using offline software algorithms, neutron pulses were identified and characterized in the data. Over the entire investigated dose range of up to 35 kGy, the detector systems were functioning and were delivering detectable neutron signals. Their performance as measured by the number of identified neutrons degrades down to about 30% of the initial value. Investigations of the irradiated components suggest that this degradation is a result of reduced optical transparency of the involved materials as well as a reduction of PMT gain due to the continuous high currents. Increasing the gain of the PMT through step-ups of the applied high voltage allowed to partially compensate for this loss in detection sensitivity even when the detectors were highly irradiated.The integrated neutron fluence during the measurement was experimentally

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Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies

Solans

Sjöstrand

Jansson

et al. 2023

Annals of Nuclear Energy

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Results of the Swedish spent fuel measurement field trials with the Differential Die-Away Self-Interrogation Instrument

Cited by 6 publications

References 8 publications

Spent Nuclear Fuel Passive Gamma Analysis And Reproducibility: Application to Skb-50 Assemblies

Spent Nuclear Fuel Passive Gamma Analysis And Reproducibility: Application to Skb-50 Assemblies

Evaluation of the in-situ Performance of Neutron Detectors based on EJ-426 Scintillator Screens for Spent Fuel Characterization

Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies

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