Nondestructive assay of spent nuclear fuel with gamma-ray spectroscopy

Willman, Christofer; Håkansson, Ane; Osifo, Otasowie; Bäcklin, A.; Svärd, Staffan Jacobsson

doi:10.1016/j.anucene.2005.12.005

Cited by 64 publications

(19 citation statements)

References 2 publications

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“…The simulation methodology is shown in Figure 6. First, a two-dimensional TransLAT simulation [14] was used to determine the expected fuel isotopics as a function of fuel burn-up and radial position in the fuel pin. Based on the isotopic distributions, the beta source term and gamma source term were calculated using ORIGEN and MCNP5, and the X-ray fluorescence source term was determined.…”

Section: Simulation Methodologymentioning

confidence: 99%

Direct Measurement of Plutonium in Spent Fuel with X-ray Fluoresence

Romano¹,

Stafford

Солодов³

et al. 2010

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Section: Simulation Methodologymentioning

confidence: 99%

Direct Measurement of Plutonium in Spent Fuel with X-ray Fluoresence

Romano¹,

Stafford

Солодов³

et al. 2010

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“…The 137 Cs is generally used as a measure of the burnup because an almost linear relationship exists between 137 Cs buildup and the burnup. The 154 Eu and 134 Cs are exploited in the 154 Eu/ 137 Cs and 134 Cs/ 137 Cs isotopic ratios, respectively, and are used to help determine burnup, initial enrichment, and cooling time (BU, IE, and CT, respectively, as used in equations) [6,7,10,11,12]. The longer half-life of the 154 Eu compared with 134 Cs makes the 154 Eu/ 137 Cs ratio, which is perhaps also suitable for longer cooling times (up to ~50 years), also useful.…”

Section: Introductionmentioning

confidence: 99%

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

Favalli

Grogan

et al. 2016

Nuclear Instruments and Methods in Physics Research Section A:

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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 137 Cs count rate and the 154 Eu/ 137 Cs, 134 Cs/ 137 Cs, 106 Ru/ 137 Cs, and 144 Ce/ 137 Cs 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.

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“…For obtaining 235 U content in uranium materials, the delayed gamma spectra (Willman 2005;Liew 1991) of uranium fission products should be analyzed. Research results on delayed gamma spectra can be applied in numerous technical fields, such as verification of nuclear weapons, safe management of nuclear materials, monitoring of customs goods, nuclear reactors projects, and retirement of nuclear facilities (Gmar 1999;Slaughter 2005;Terremoto 1999).…”

Section: Introductionmentioning

confidence: 99%

Decay Chain Deduction of Uranium Fission Products

et al. 2016

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Delayed gamma spectrum is the fingerprint of uranium materials in arms control verification technology. The decay chain is simplified into basic state linear chain and excitation state linear chain to calculate and analyze the delayed gamma spectra of fission products. Formulas of the changing rule for nuclide number before and after zero-time are deduced. The C program for calculating the delayed gamma ray spectra data is constructed, and related experiments are conducted to verify this theory. Through analysis of the delayed gamma counts of several nuclides, the calculated results are found to be consistent with experimental values.

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Nondestructive assay of spent nuclear fuel with gamma-ray spectroscopy

Cited by 64 publications

References 2 publications

Direct Measurement of Plutonium in Spent Fuel with X-ray Fluoresence

Direct Measurement of Plutonium in Spent Fuel with X-ray Fluoresence

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

Decay Chain Deduction of Uranium Fission Products

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