scispace - formally typeset
Open AccessJournal ArticleDOI

Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

TLDR
The Next Generation Safeguards Initiative (NGSI) -Spent Fuel (SF) project as discussed by the authors has developed a set of measurement campaigns at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB).
Abstract
The purpose of the Next Generation Safeguards Initiative (NGSI)–Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/137Cs, 134Cs/137Cs, 106Ru/137Cs, and 144Ce/137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity’s behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. The results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.

read more

Content maybe subject to copyright    Report

Citations
More filters
Journal ArticleDOI

PWR and BWR spent fuel assembly gamma spectra measurements

TL;DR: In this paper, the authors focused on spectrally resolved gamma-ray measurements performed on a diverse set of 50 spent fuel assemblies [25 pressurized water reactor (PWR) assemblies and 25 boiling water Reactor (BWR), and these same 50 assemblies will be measured with neutron-based NDA instruments and a full-length calorimeter.
Journal ArticleDOI

Advancing the Fork detector for quantitative spent nuclear fuel verification

TL;DR: In this article, a data analysis module based on the ORIGEN burnup code was implemented to provide automated real-time analysis of Fork detector data, which allows quantitative predictions of expected neutron count rates and gamma units as measured by the Fork detectors using safeguards declarations and available reactor operating data.
Journal ArticleDOI

Determination of spent nuclear fuel parameters using modelled signatures from non-destructive assay and Random Forest regression

TL;DR: In this paper, the verification of fuel parameters is a central undertaking for nuclear inspectors aiming at verifying the completeness and correctness of operator declarations, and the verification is done by verifying the correctness of the operator declarations.
Journal ArticleDOI

Delayed gamma-ray spectroscopy with lanthanum bromide detector for non-destructive assay of nuclear material

TL;DR: In this article, the measured performance of a 2" × 2" γ-ray detector system, coupled with a negatively biased PMT and a tapered active high voltage divider, with count-rates up to ∼ 3 Mcps.
Journal ArticleDOI

Dose Deposition Profiles in Untreated Brick Material.

TL;DR: It was found that by using thermoluminescence responses, the dose deposition profile of a brick sample could be reconstructed without any chemical treatment, and has the potential to greatly expedite dose reconstructions in the wake of nuclear accidents.
References
More filters
Book

Passive Nondestructive Assay of Nuclear Materials

TL;DR: This book emphasizes passive NDA techniques, although certain active techniques like gamma-ray absorption densitometry and x-ray fluorescence are discussed here because of their intimate relation to passive assay techniques.
Journal ArticleDOI

Investigation of the PGNAA using the LaBr3 scintillation detector.

TL;DR: The paper investigates the applicability of the LaBr(3) scintillation detector to PGNAA and finds it applicable to both neutron inelastic scattering and neutron capture.
ReportDOI

Application of nondestructive gamma-ray and neutron techniques for the safeguarding of irradiated fuel materials

TL;DR: In this article, the axial activity profiles of fuel assemblies have been developed using ion chambers and Be(..gamma..,n) detectors, and detailed measurements using high-resolution gamma-ray spectrometry and passive neutron techniques were correlated with operator-declared values of cooling times and burnup.
Journal ArticleDOI

Wide energy range efficiency calibration for a lanthanum bromide scintillation detector

TL;DR: In this article, the absolute full-energy peak efficiency calibration of a 38.1 mm × 38. 1 mm (1.5 in × 1.5in ) LaBr3:Ce crystal for gamma-ray energies up to 5
Journal ArticleDOI

Generation of improved isotopic molybdenum covariances from elemental cross-section data using SAMMY

TL;DR: In this article, a new uranium-molybdenum fuel form to be produced at the Y-12 National Security Complex (Y-12) at the U.S.
Related Papers (5)