Multimodal Material Identification Reconstruction Algorithms
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Klasky, Marc Louis↗
Engineering topics
James, Michael R.
Publications and source records attributed to James, Michael R..
Current and Emerging Counting Capabilities within C-NR
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Flanagan, Dylan Cole↗
LANSCE Target 2 and Target 4 Engineering and Irradiations
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Dale, Gregory E.↗
Efficiency Studies of Fast Neutron Tracking Using MCNP
Fast neutron identification and spectroscopy is of great interest to nuclear physics experiments. Using the neutron elastic scattering, the fast neutron momentum can be measured. Wang and Morris introduced the theoretical concept that the initial fast neutron momentum can be derived from up to three consecutive elastic collisions between the neutron and the target, including the information of two consecutive recoil ion tracks and the vertex position of the third collision or two consecutive elastic collisions with the timing information. Here, we also include the additional possibility of measuring the deposited energies from the recoil ions. In this paper, we simulate the neutron elastic scattering using the Monte Carlo N-Particle Transport Code (MCNP) and study the corresponding neutron detection and tracking efficiency. The corresponding efficiency and the scattering distances are simulated with different target materials, especially natural silicon (92.23%28Si, 4.67%29Si, and 3.1%30Si) and helium-4 (4He). The timing of collision and the recoil ion energy are also investigated, which are important characters for the detector design. We also calculate the ion traveling range for different energies using the software, “The Stopping and Range of Ions in Matter (SRIM)”, showing that the ion track can be most conveniently observed in 4He unless sub-micron spatial resolution can be obtained in silicon.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Column separation of tetravalent cerium fission products from trivalent rare earth radio-isotopes
Rapid and efficient isolation of individual rare earth element (REE) radioisotopes from complex mixtures is necessary to support the fields of nuclear forensics, medical isotope production and nuclear physics measurements. The separations must be robust and generate sufficiently high purity samples for subsequent radiological analysis. Current methodologies utilize a laborious two step Ce(IV)-iodate precipitation followed by Ce(IV)-nitrate di-(2-ethylhexyl)phosphoric acid/n-heptane extraction. This work reports an alternative method to isolate Ce fission product isotopes equilibrated with milligrams of cold carrier, from the remaining REE’s using a Ce(IV)/LN-resin (Eichrom Technologies) based separation. Optimization of Ce(IV) loading, REE(III) elution volume and subsequent Ce(III) stripping step utilized 166m Ho tracer. Mixed fission product experiments provided a further test of this LN-resin method, with analysis of purified 141/144 Ce, 147 Nd and 91 Y. Overall, while decontamination factors were lower for the LN-resin method, (vs. the combined precipitation/extraction) the simplicity of the technique and the satisfactory fission product analysis results point to the efficacy of this method.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
LANL Countroom Gamma-Gamma Coincidence Capabilities [Slides]
Abstract not provided.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Isolation and characterization of a californium metallocene
Californium (Cf) is currently the heaviest element accessible above microgram quantities. Cf isotopes impose severe experimental challenges due to their scarcity and radiological hazards. Consequently, chemical secrets ranging from the accessibility of 5f/6d valence orbitals to engage in bonding, the role of spin–orbit coupling in electronic structure, and reactivity patterns compared to other f elements, remain locked. Organometallic molecules were foundational in elucidating periodicity and bonding trends across the periodic table, with a twenty-first-century renaissance of organometallic thorium (Th) through plutonium (Pu) chemistry, and to a smaller extent americium (Am), transforming chemical understanding. Yet, analogous curium (Cm) to Cf chemistry has lain dormant since the 1970s. Here, we revive air-/moisture-sensitive Cf chemistry through the synthesis and characterization of [Cf(C 5 Me 4 H) 2 Cl 2 K(OEt 2 )] n from two milligrams of 249 Cf. This bent metallocene motif, not previously structurally authenticated beyond uranium (U), contains the first crystallographically characterized Cf–C bond. Analysis suggests the Cf–C bond is largely ionic with a small covalent contribution. Lowered Cf 5f orbital energy versus dysprosium (Dy) 4f in the colourless, isoelectronic and isostructural [Dy(C 5 Me 4 H) 2 Cl 2 K(OEt 2 )] n results in an orange Cf compound, contrasting with the light-green colour typically associated with Cf compounds.
Chemical bonding↗
Spectral characterization of flash and high flux x-ray radiographic sources with a magnetic Compton spectrometer
In this article, we present a new analysis method applied to revitalize permanent magnet Compton spectrometers used to measure photon energy spectra in the MeV range. The inversion of the measured electron distribution to determine the original photon distribution is achieved via a method of consistent coupled radiation transport and magnetic field mapping of the input photon spectra to the measured electron distribution. The method of linear least squares was used to perform the unfolding of the electron distribution to the initial photon spectra, without any assumptions made regarding the electron distribution. We present an application of this method to data from a nominal 19.4 MeV flash radiographic source (the first axis of the Dual Axis Radiographic Hydro-Test Facility) capable of generating 500 R @ 1 m in ~60 ns and a medical therapy source (a Scanditronix M22, Microtron) capable of variable energies with nominal endpoints of 6, 10, 15, and 20 MeV and an output of ~1000–2000 R/min @ 1 m. The results provide agreement between the modeled and unfolded experimentally measured photon spectra as quantified by statistical tests, from 1.5 to 20 MeV. Experimental results are presented as well as a discussion of the novel MCNP6-based simulations and methods for reconstruction of the spectra.
47 OTHER INSTRUMENTATION↗
Monte Carlo Modeling and Design of Photon Energy Attenuation Layers for >10× Quantum Yield Enhancement in Si-Based Hard X-ray Detectors
High-energy (>20 keV) X-ray photon detection at high quantum yield, high spatial resolution, and short response time has long been an important area of study in physics. Scintillation is a prevalent method but limited in various ways. Directly detecting high-energy X-ray photons has been a challenge to this day, mainly due to low photon-to-photoelectron conversion efficiencies. Commercially available state-of-the-art Si direct detection products such as the Si charge-coupled device (CCD) are inefficient for >10 keV photons. Here, we present Monte Carlo simulation results and analyses to introduce a highly effective yet simple high-energy X-ray detection concept with significantly enhanced photon-to-electron conversion efficiencies composed of two layers: a top high-Z photon energy attenuation layer (PAL) and a bottom Si detector. We use the principle of photon energy down conversion, where high-energy X-ray photon energies are attenuated down to ≤10 keV via inelastic scattering suitable for efficient photoelectric absorption by Si. Our Monte Carlo simulation results demonstrate that a 10–30× increase in quantum yield can be achieved using PbTe PAL on Si, potentially advancing high-resolution, high-efficiency X-ray detection using PAL-enhanced Si CMOS image sensors.
47 OTHER INSTRUMENTATION↗
C-NR Countroom Overview [Slides]
Perform qualitative and quantitative assay of gamma, beta, and alpha-emitting radionuclides in a variety of matrices and over a wide range of activity levels.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
(U) Segmented Scintillator Pitch, Thickness, and Septa Material Effects on the Swank Factor, Quantum Efficiency, and DQE(0) for High-Energy X-Ray Radiography
Scintillator design is an important aspect in constructing a radiographic facility in order to collect the most robust data possible. For the proposed Enhanced Capabilities for Sub-critical Experiment (ECSE) facility in Nevada, we explored a permutation of 13 segmented scintillator designs in order to understand the best performance and trade offs for each design. We calculated the quantum efficiency, Swank factor, and detective quantum efficiency at zero-frequency (DQE(0)) for each scintillator design in order to compare performance.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Countroom Gamma Spectroscopy Library Updates
The C-NR Countroom analyzes gamma spectroscopy data using three codes, SAP (which is the combination of SPECANAL and RAYGUN), GAMANAL and UNISAMPO. The codes use libraries which are chosen by the user of gamma emission data to do the identification and quantification. The Countroom maintains nine unique libraries for use in analysis. Historically, the values contained in these libraries has not been consistently updated and many values are quite old and do not reflect the state-of-the-art.
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗
(U) Endpoint Energy and Scintillator Geometry Effects on the Swank Factor, Quantum Efficiency, and DQE(0) for High-Energy Radiography
High-energy radiography is used to image imploding materials to better understand weapon design and performance. The Enhanced Capabilities for Subcritical Experiments (ECSE) is a new facility proposal that aims to collect radiographic images of nuclear material. As part of the facility design, we aim to optimize data quality and radiographic performance by investigating different detector designs. We addressed design decisions by simulating different scintillator designs using M CNP6 and calculated the quantum efficiency, Swank factor, and detective quantum efficiency at zero-frequency (DQE(O)). First, we investigated the effects of the x-ray endpoint energy on the detector response. We generated three x-ray spectra with endpoint energies of 20 MeV, 22 MeV, and 24 MeV. The three raw spectra were filtered using the Dual-Axis Radiographic Hydrodynamic Test facility (DARHT) line-of-sight materials along with 1) flat field filtration using 7 cm tungsten alloy in the bullnose and 2) an FTO with 4 plates. The scatter-to-direct radiation ratio was much larger for FTO with 4 plates (50-60%) compared to the flat field with 7 cm of bullnose material (8%). We used these filtered spectra to calculate the detector response for the original DARHT segmented scintillator design. We found that the endpoint energy and filtration had a negligible effect on the detector response. The quantum efficiency was 0.63, the Swank factor was 0.84, and the DQE(O) was 0.53 for all six spectra.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Comparison of Modeled to Measured Spectra using MCNP and GADRAS to Benchmark and Contrast Modeling Limitations
The desire to improve nuclear material detection through portal monitors and other low resolution detectors has led to interest in benchmarking the performance of radiation transport codes. These codes can be used to generate a variety and quantity of spectra that may be cost prohibitive to measure directly. Particular characteristics of typical detection scenarios were isolated to compare the performance of radiation transport codes to laboratory experiments. These benchmark experiments were performed to validate simulations in a number of key areas. These experiments included high areal density configurations in both one- and three-dimensional configurations. In addition, off-angle measurements were conducted to investigate the impact of detector response assumptions on complex geometries, for example where an unknown source is not physically collocated with an apparent hot spot. Furthermore, by examining both simple shielding and backscatter configurations, isolation of the scatter emanating from the object and environmental background scatter contributions to the spectra could be elucidated. A series of experiments were performed in which the order of shielding layers and the thickness were evaluated to examine the ability of the simulations to address these variables. Experiments with increasing thickness of polyethylene around a neutron source also allows for examinations of the ability of the transport simulations to properly model n,γ reactions. Finally, depleted uranium (DU) measurements have more complicated spectra than the cobalt-60 and consequently allow for investigations into the ability of transport simulations to model self-shielding. In each case, the results of the experiments were compared to MCNP simulations to judge the performance of the code, as was done previously with GADRAS 18.7.9 simulations [7]. All of the benchmark measurements were taken with a liquid nitrogen cooled 140% high purity germanium (HPGe) detector with a bismuth collimator that had the front tin filter removed. The measurement location and detector configuration were subsequently used for all experimental configurations. The remainder of this report details the experimental measurements, Section 2 and the MCNP model, Section 3. Comparisons between the experimental results and MCNP-generated spectra are performed, Section 4. Section 5 compares the results obtained with MCNP with the previously reported results obtained with GADRAS [2]. Finally, Section 6 presents the conclusions.
61 RADIATION PROTECTION AND DOSIMETRY↗
Summing Corrections For La-140 On Counter 137 [Slides]
The counting of filters for gamma activity is often done with the sample situated very close or wrapped around the detector. This improves the counting statistics but can increase the probability of summing and affect the calculation of yield. An MCNP model of counter 137 (a 65% HPGe detector) was used to compute the total and peak efficiencies for two sample types, 40 and 20. The type 40 is a long filter strip wrapped in a Marinelli beaker which sits around the detector in an annular fashion. The type 20 is a 8.4 in radius filter, quarter-folded and placed flat on the detector face. A comparison of the peak efficiency computed in MCNP was compared to the measured efficiency to ensure consistency. Using the measured peak efficiency and MCNP-computed total efficiency, the TrueCoinc program was run to estimate the summing values for La-140 peaks. The results showed the summing out of two peaks (487 and 1596 keV) was around 6-8% in for both sample types.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
June 2019 Depleted Uranium Irradiation
Three different irradiations were performed at the Annular Core Research Reactor (ACRR) at Sandia National laboratory on June 4-6, 2019. Each target assembly included two or three depleted uranium targets, as well as a bismuth target and dosimetry packets. In July 2019, the target assemblies were received at TA-48 RC-1, unpackaged, and radiochemical analyses were performed. The analyses included autoradiography and gamma counting of the whole depleted uranium targets, gamma counting of the activation foils, and dissolution of six of the depleted uranium targets, followed by separated radiochemical analysis for a suite of fission products. This report describes the details of the radiochemical analysis and provides final results for the fission and activation product concentrations.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
Final Results for 99 Mo, 111 Ag, 147 Nd, 140 Ba
Seven depleted uranium targets were irradiated at the ACRR reactor in three different irradiations occurring on June 4th, 5th, and 6th, 2019. The targets were received at LANL on July 10, 2019, unpackaged, and analyzed by autoradiography and gamma-ray spectrometry. Table 1 shows a chart of the Target ID, target mass, time the irradiation occurred, and the corresponding LANL sample ID. Six of the targets were dissolved and chemically separated radiochemical analyses were performed for a suite of radionuclides on four of the targets. The final results of the radiochemical separation and analysis of 99 Mo, 111 Ag, 147 Nd and 140 Ba for depleted U samples 4416-01, 4417-01, 4418-01 and 4418-03 are presented in Table 2. Associated errors represent 1σ uncertainty.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
Activation Foil Report for the June 2016 IER-151NCERC Irradiation
A critical experiment was conducted at NCERC on 6 Jun 2016. In this experiment, two sets of activation foils (Cu, Ni, Sc and Ti) were placed within the core. After the irradiation, the foils were withdrawn, packaged and set to the LANL C-NR Countroom and the foils were counted over a period of a few weeks. The results were tabulated and a simple MCNP model was created to simulate a neutron spectrum consistent with the foil results.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗