FIGARO: detecting nuclear materials using high-energy gamma-rays

Micklich, B.J.; Smith, D.L.; Massey, T. N.; Fink, C.L.; Ingram, David C.

doi:10.1016/s0168-9002(03)01122-7

Cited by 27 publications

(7 citation statements)

References 4 publications

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“…A considerable body of work exists on active interrogation to detect the presence of fissile isotopes in various environments. In cargo screening, for example, the primary goal is one of detection so that the collection of any induced-fission signature-delayed or prompt neutrons, delayed or prompt gamma rays, or some combination thereof-achieves the goal of alarming on anomalous vehicles or packages [2]- [4]. Similar methods are used for remote assays of actinide content in nuclear waste [5], [6].…”

Section: Introductionmentioning

confidence: 99%

High-Energy Delayed Gamma Spectroscopy for Spent Nuclear Fuel Assay

Campbell

Smith

Misner

2011

IEEE Trans. Nucl. Sci.

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High-accuracy, direct, nondestructive measurement of fissile and fissionable isotopes in spent fuel, particularly the Pu isotopes, is a well-documented, but still unmet challenge in international safeguards. As nuclear fuel cycles propagate around the globe, the need for improved materials accountancy techniques for irradiated light-water reactor fuel will increase. This modeling study investigates the use of delayed gamma rays from fission-product nuclei to directly measure the relative concentrations of 235 U, 239 Pu, and 241 Pu in spent fuel assemblies. The method is based on the unique distribution of fission-product nuclei produced from fission in each of these fissile isotopes. Fission is stimulated in the assembly with a pulse-capable source of interrogating neutrons. The measured distributions of the short-lived fission products from the unknown sample are then fit with a linear combination of the known fission-product yield curves from pure 235 U, 239 Pu, and 241 Pu to determine the original proportions of these fissile isotopes. Modeling approaches for the intense gamma-ray background promulgated by the long-lived fission-product inventory and for the high-energy gamma-ray signatures emitted by short-lived fission products from induced fission are described. Benchmarking measurements are presented and compare favorably with the results of these models. Results for the simulated assay of simplified individual fuel rods ranging from fresh to 60-GWd/MTU burnup demonstrate the utility of the modeling methods for viability studies, although additional work is needed to more realistically assess the potential of High-Energy Delayed Gamma Spectroscopy (HEDGS).Index Terms-Gamma-ray spectroscopy, nondestructive assay, nuclear fuel cycle safeguards, nuclear fuels.

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Section: Introductionmentioning

confidence: 99%

High-Energy Delayed Gamma Spectroscopy for Spent Nuclear Fuel Assay

Campbell

Smith

Misner

2011

IEEE Trans. Nucl. Sci.

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“…The probing radiation source used for this work was based on the FIGARO concept, originally proposed by researchers at Argonne National Laboratory [8]. Protons are accelerated into a fluorine-containing target to produce γ-rays of 6.13, 6.92, and 7.12 MeV via the 19 F(p,αγ) 16 O reaction [9], [10].…”

Section: A Probing Radiation Sourcementioning

confidence: 99%

Detectors for intense, pulsed active detection

Jackson

Allen

Apruzese

et al. 2010

IEEE Nuclear Science Symposuim &Amp; Medical Imaging Conference

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In intense, pulsed active detection, a single, intense pulse of radiation is used to induce photofission in fissionable material, increasing its detectability. The Mercury pulsed-power generator was converted to positive polarity (+3.7 MV, 325 kA, 50-ns FWHM) to drive an intense, pulsed radiation source based on the FIGARO active detection concept. The probing radiation source consisted of an ion-beam diode and a thick PTFE (Teflon) converter where 6 -7 MeV γ-rays were produced via the 19 F(p,αγ) 16 O reaction. A suite of radiation detectors was used both to detect the presence of irradiated fissionable material and to characterize the probing radiation source. Four types of detectors were used for the source characterization. Thermoluminescent dosimeters were used to measure the angular distribution of the dose associated with x-rays and γ-rays from the ion-beam diode. Plastic scintillator-photodiode detectors were used to characterize the time dependence of this dose. A plastic scintillator-photomultiplier detector was used to monitor the γ-ray intensity of the probing radiation source and to monitor changes in the production of background neutrons by the diode and PTFE converter. A set of rhodium foil activation counters was used to measure the absolute yield of these background neutrons. Two types of detectors with comparable sensitivities were used to measure delayed neutrons resulting from photofission: 3 He proportional counters and a 6 Li-loadedglass-scintillator detector. The neutron detection rate from each detector following the probing radiation pulse was over 100 times higher with depleted uranium present than with lead.

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“…Tables 2 and 3 summarize the target yields and efficiencies for all the target materials tested. Yields for 4 MeV protons on MgF 2 [3] were included to compare our low-energy gamma production to that from a highvoltage accelerator. The latter accelerator may be more appropriate for applications requiring extremely high Table 1 Gamma energy peak distributions and proton energy of lowest significant peak in production cross-section for reactions most appropriate for lowenergy proton gamma tube photon fluxes [4], but this system is larger, more complex, will likely produce more background from activation, and would normally produce much lower beam current.…”

Section: Target Materials and Gamma-ray Yieldsmentioning

confidence: 99%