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At least 667 records · Page 37
All sourcesNASA NTRSDOE OSTI
DOE OSTI2021

Comparison of the Capacitances and Switching Losses of 1.2 kV Common-Source and Common- Drain Bidirectional Switch Topologies

Bidirectional, or four-quadrant switches (FQS) can be designed as back-to-back MOSFETs connected in common-drain (CD) or common-source (CS) topologies. CDFQS and CS-FQS assembled from discrete 1.2 kV commercially available SiC power MOSFETs were characterized to obtain capacitance and switching loss values. The CD-FQS exhibited a 1.17x larger turn-on loss compared to the CS-FQS, while the CS-FQS exhibited a 1.52x larger turn-off loss compared to the CD-FQS. The CS-FQS exhibited a lower input capacitance, while the CD-FQS exhibited a lower output and reverse transfer capacitance.

Silicon Carbide, Bidirectional Switch, Switching P↗
DOE OSTI2021

Ion Exchange Processing of AP-105 Hanford Tank Waste through Crystalline Silicotitanate in a Staged 2- then 3-Column System

The U.S. Department of Energy (DOE) is working to expedite processing of Hanford tank waste supernate at the Hanford Waste Treatment and Immobilization Plant (WTP). To support this goal, Washington River Protection Solutions, LLC (WRPS, Richland, WA) is designing a system for suspended solids and cesium (Cs/ 137 Cs) removal from Hanford tank waste supernate. The effluent will then be sent to the WTP Low-Activity Waste (LAW) Facility for vitrification. The Cs removal is critical for eliminating the high dose rate associated with 137 Cs and facilitating a contact maintenance philosophy for the LAW Facility. The maximum 137 Cs concentration in the LAW sent to the WTP is targeted to be below the 3.18E-5 Ci 137 Cs/mole of Na waste acceptance criteria (WAC) limit. The filtration and ion exchange systems will be placed near the Hanford tanks and are collectively termed the Tank Side Cesium Removal (TSCR) system.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Crystalline Silicotitanate Batch Contact Testing with Ba, Ca, Pb, and Sr

Washington River Protection Solutions is working to support initial production of immobilized low-activity waste (LAW) by feeding Hanford tank supernate from tank farms to the Hanford Waste Treatment and Immobilization Plant (WTP) LAW Facility. This goal incorporates the design of a Tank Side Cesium Removal system, which filters tank waste supernate to remove suspended solids and then removes Cs by processing it through crystalline silicotitanate (CST) ion exchange media manufactured by Honeywell UOP, LLC. The 137 Cs-depleted product is intended to be sent to the WTP for vitrification. Processing of actual tank waste supernate showed effectively complete uptake of Sr and Ba by CST and significant uptake of Ca. Further, Campbell et al. (2019) analyzed CST post-column testing and found significant (>1E-2 mmoles/g) uptake of Ca and Pb along with some Ba, Cd, Fe, Sr, and U. This led to concern that selected metals, particularly the +2 cations, Ca, Sr, Ba, and Pb may be consuming Cs exchange sites and possibly reducing CST capacity for Cs. Exchange of +2 cations was assumed to be associated with the M(OH) + species for the metal (M) ion in the caustic solution. A series of batch contact testing was conducted to evaluate the exchange behavior of Ba, Ca, Pb, and Sr onto CST. The Cs exchange behavior was also tested as a benchmark for direct comparisons. The CST was provided in the sodium form by Honeywell UOP, as IONSIV TM R9140-B, Lot 2002009604, 18 x 50 mesh. A <30-mesh aliquot was collected to match the sieve fraction expected for use in upcoming small column test configurations. Kinetic exchange rate and isotherms were measured at metal concentrations benchmarked from the AP-107 tank waste feed composition and as limited by the metal solubility in the alkaline solution. Two simplified matrices were tested: 1) 1.0 M NaOH/4.6 M NaNO 3 and 2) 0.1 M NaOH/5.5 M NaNO 3 ; these matrices represented the expected 5.6 M Na concentration of process feed and served to address the hydroxide concentration effect on exchange behavior.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2021

Characterization of Tank 9H Dissolution Batches in Support of Tank Closure Cesium Removal (TCCR) 1A Batch 1 Preparations

Savannah River Remediation (SRR) is currently preparing the first batch of material to be processed through the Tank Closure Cesium Removal (TCCR) 1A system. The feed for TCCR 1A will consist of dissolved saltcake from Tank 9H. Two batches of salt (Batch 1A and Batch 1B) have been dissolved in Tank 9H and subsequently transferred to Tank 10H to prepare Batch 1 for TCCR 1A. Savannah River National Laboratory (SRNL) received samples from each batch of dissolved salt prior to transfer for characterization. SRNL received both a surface and a variable depth sample from Batches 1A and 1B. In both cases no solids were observed in the surface sample, but were observed in the depth sample. For Batch 1A the variable depth sample was only slightly cloudy, while for Batch 1B the variable depth sample contained a significant amount (10.14 wt%) of solids. The solids were determined to be primarily aluminum containing phases, with only a small fraction (0.22 wt%) being sludge solids. In general, the samples from Batch 1A were more concentrated salt solutions than Batch 1B, with sodium concentrations of 8.53 and 8.57 M for the surface and filtered depth samples in Batch 1A, respectively. The sodium concentrations in Batch 1B samples ranged from 4.27 M for the surface sample to 7.57 M for the depth sample filtrate, indicating some stratification within the tank. The 137 Cs activity as well as the total Cs concentration in the filtered Batch 1A depth sample were approximately double the activity and concentration measured in the filtrate from the Batch 1B depth sample. The total Cs concentration in the Batch 1A depth sample filtrate was 22.4 mg/L, while for the Batch 1B depth sample filtrate the total Cs concentration was calculated to be 12.0 mg/L. These Cs concentrations are significantly higher than was measured in Batches 1-3 from Tank 10H dissolved saltcake which was previously processed through the original TCCR unit.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2022

Options for the Removal of Cesium and Strontium from Acidic Uranyl Sulfate Solutions from Molybdenum-99 Production

A small laboratory-scale column process aimed at removing fission products from prototypical acidic sulfate solution wastes from a prototypical Mo-99 recovery process has been operated in a radioactive materials hood at Savannah River National Laboratory. This equipment has been operated with realistic concentrations of uranium (0.4 wt % 235 U), plutonium ( 239 Pu), neptunium ( 237 Np), non-radioactive surrogates of common fission products (including Cs and Sr) and two promising absorbents AMP-PAN and CST R91290-B. The goal of this work was to demonstrate the removal and concentration of high specific activity isotopes which are expected to dominate the classification of the low-level waste from the production of 99 Mo. Both AMP-PAN and CST R9120-B are attractive absorbents for the removal of 137 Cs from an acidic sulfate waste stream. They do not provide a solution for the removal of 90 Sr from the acidic solutions, but CST should be investigated at a higher pH. Limited removal of transuranic species and almost no removal of uranium was observed in this testing. This could be important due to the relatively large amount of uranium expected to be present in such waste streams. The capacity of these absorbents for 137 Cs will likely be dependent on the Cs concentration in the solutions processed but loading in the range of 0.2 to 5 mg Cs per gram of absorbent appears to be achievable.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2022

Proposed Products to Support Shelter-Evacuation Decision Making in the Event of a Nuclear Detonation

Response strategies implemented in the first few hours to days after a nuclear detonation on the US homeland may save more than 100,000 lives. Effective planning and pre-event capability development can increase the response efficacy and so the number of lives saved. During such an event, the US Department of Defense, Joint Task Force Civil Support (DoD JTF-CS) provides command and control for the DoD forces supporting civil authority response operations. Among other activities, JTF-CS expects to support FEMA as well as State and local agencies in shelter and evacuation response activities. JTF-CS currently uses a manual method to generate evacuation decision making products. This method compares the dose that would be (a) acquired remaining at a given location to that (b) acquired during evacuation along a small number of routes. In these products, evacuation may be warranted when the projected “remain” dose is greater than the “evacuate” dose. This method only provides a limited consideration of the protection buildings provide their occupants. To inform the JTF-CS nuclear detonation response, the DoD Defense Threat Reduction Agency (DTRA) has tasked Lawrence Livermore National Laboratory (LLNL) to design a set of planning and response products to support shelter-evacuation activities. This report documents these products to facilitate DTRA and JTF-CS planning efforts. To provide context, we also provide appendices that summarize US planning guidance response zones, early (<72 h) response strategies, and other key topics.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2023

Multi-scale fission product release model with comparison to AGR data

TRistructural ISOtropic (TRISO) particle fuel is central to several advanced, high-temperature reactor designs. Each particle consists of a fuel kernel encapsulated by three layers of carbon and ceramics that prevent the release of fission products and ensure physical integrity. Despite outstanding retention properties, fission product release has been observed from intact particles. To better understand and quantify fission product release from TRISO particles, a multiscale, mechanistic model of fission product transport is being developed by the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. Previous work focused on silver (Ag) transport and improved Ag release predictions. The work described in this report builds on this experience to better understand cesium (Cs) transport in silicon carbide (SiC), the main barrier to the release of fission products. Atomistic simulations provide bulk and grain boundary (GB) Cs diffusivities in SiC, which are used by phase field simulations in the mesoscale code Marmot to determine the temperature, microstructure, and irradiation-dependent Cs diffusivity at the mesoscale in SiC. This approach attributes the different temperature regimes experimentally observed for Cs diffusivities in SiC to a transition from bulk-dominated diffusivity at high temperatures to a GB-dominated regime at low temperatures, providing new insight. The multiscale, mechanistic effective diffusivity is then implemented in the fuel performance code BISON and further validated by comparing Cs release predictions from Advanced Gas Reactor (AGR)-1 and AGR-2 post-irradiation measurements. The new model improves BISON’s predictability. This document also reports improvements made on Ag transport modeling by accounting for different GB types having different diffusivities. Moreover, this report details preliminary efforts to model palladium (Pd) attack of the SiC at the mesoscale using a phase field approach. Pd attack and its impact on accelerated Ag transport remains a misunderstood phenomenon, and we use the model to demonstrate that the formation of lamellae that has been observed in experiments can be explained by the reaction of Pd with SiC to form alternating layers of graphite and Pd 2 Si. This effort aims to improve our understanding of the reaction and eventually provide a model for BISON to account for Pd penetration and its effects on fission product release.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2023

High levels of exfoliated fragments following glycocalyx destruction in hemorrhagic fever with the renal syndrome are associated with mortality risk

Background The glycocalyx is a gel-like structure that covers the luminal side of vascular endothelial cells. It plays an important role in maintaining the integrity of the vascular endothelial barrier structure. However, the presence or absence of glycocalyx destruction in hemorrhagic fever with renal syndrome (HFRS) and its specific mechanism and role is still unclear. Methods In this study, we detected the levels of exfoliated glycocalyx fragments, namely, heparan sulfate (HS), hyaluronic acid (HA), and chondroitin sulfate (CS), in HFRS patients and investigated their clinical application value on the evaluation of disease severity and prognosis prediction. Results The expression of exfoliated glycocalyx fragments in plasma was significantly increased during the acute stage of HFRS. The levels of HS, HA, and CS in HFRS patients during the acute stage were significantly higher than in healthy controls and convalescent stages of the same type. HS and CS during the acute stage gradually increased with the aggravation of HFRS, and both fragments showed a significant association with disease severity. In addition, exfoliated glycocalyx fragments (especially HS and CS) showed a significant correlation with conventional laboratory parameters and hospitalization days. High levels of HS and CS during the acute phase were significantly associated with patient mortality and demonstrated an obvious predictive value for the mortality risk of HFRS. Conclusion Glycocalyx destruction and shedding may be closely associated with endothelial hyperpermeability and microvascular leakage in HFRS. The dynamic detection of the exfoliated glycocalyx fragments may be beneficial for the evaluation of disease severity and prognosis prediction in HFRS.

Du, Hong↗
DOE OSTI2024

Super-hydrophobic, thermally insulating, thermal-shocks resistant well cement composites for completion of geothermal wells at hydrothermal temperatures of up to 300° C

A well cement composite and a method for making a well cement composite includes a mixture of calcium aluminate cement (CAC) and fly ash cenospheres (CS) in a weight ratio of from 30:70 to 80:20 CAC to CS; sodium metasilicate (SMS) in an amount of from 1 to 10% of the total weight of the mixture of CAC and CS; polymethylhydrosiloxane (PMHS) in an amount of from 0.5 to 6.0% of the total weight of the mixture of CAC and CS; and water in a weight ratio of from 0.5:1.0 to 1.2:1.0 of water to CAC and CS.

Pyatina, Tatiana↗
DOE OSTI2020

Materials Data on CsB(CN)4 by Materials Project

Cs(CN)4B crystallizes in the tetragonal I4_1/a space group. The structure is three-dimensional and consists of four boron molecules and one Cs(CN)4 framework. In the Cs(CN)4 framework, Cs1+ is bonded in a 8-coordinate geometry to eight equivalent N3- atoms. There are four shorter (3.30 Å) and four longer (3.44 Å) Cs–N bond lengths. C2+ is bonded in a single-bond geometry to one N3- atom. The C–N bond length is 1.17 Å. N3- is bonded in a distorted single-bond geometry to two equivalent Cs1+ and one C2+ atom.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Materials Data on Cs4Ta2S11 by Materials Project

Cs4Ta2S11 crystallizes in the orthorhombic Pca2_1 space group. The structure is three-dimensional. there are four inequivalent Cs1+ sites. In the first Cs1+ site, Cs1+ is bonded in a 8-coordinate geometry to eight S+1.27- atoms. There are a spread of Cs–S bond distances ranging from 3.44–4.07 Å. In the second Cs1+ site, Cs1+ is bonded in a 8-coordinate geometry to eight S+1.27- atoms. There are a spread of Cs–S bond distances ranging from 3.56–3.93 Å. In the third Cs1+ site, Cs1+ is bonded in a 8-coordinate geometry to eight S+1.27- atoms. There are a spread of Cs–S bond distances ranging from 3.60–4.04 Å. In the fourth Cs1+ site, Cs1+ is bonded in a 9-coordinate geometry to nine S+1.27- atoms. There are a spread of Cs–S bond distances ranging from 3.56–3.98 Å. There are two inequivalent Ta5+ sites. In the first Ta5+ site, Ta5+ is bonded in a 7-coordinate geometry to seven S+1.27- atoms. There are a spread of Ta–S bond distances ranging from 2.26–2.84 Å. In the second Ta5+ site, Ta5+ is bonded in a 7-coordinate geometry to seven S+1.27- atoms. There are a spread of Ta–S bond distances ranging from 2.26–2.85 Å. There are eleven inequivalent S+1.27- sites. In the first S+1.27- site, S+1.27- is bonded in a 5-coordinate geometry to three Cs1+, one Ta5+, and one S+1.27- atom. The S–S bond length is 2.08 Å. In the second S+1.27- site, S+1.27- is bonded in a 1-coordinate geometry to four Cs1+, one Ta5+, and one S+1.27- atom. In the third S+1.27- site, S+1.27- is bonded in a 5-coordinate geometry to three Cs1+, one Ta5+, and one S+1.27- atom. The S–S bond length is 2.09 Å. In the fourth S+1.27- site, S+1.27- is bonded in a 1-coordinate geometry to three Cs1+, one Ta5+, and one S+1.27- atom. The S–S bond length is 2.09 Å. In the fifth S+1.27- site, S+1.27- is bonded in a 1-coordinate geometry to three Cs1+, one Ta5+, and one S+1.27- atom. In the sixth S+1.27- site, S+1.27- is bonded in a distorted L-shaped geometry to three Cs1+ and two Ta5+ atoms. In the seventh S+1.27- site, S+1.27- is bonded in a distorted single-bond geometry to three Cs1+ and one Ta5+ atom. In the eighth S+1.27- site, S+1.27- is bonded in a 1-coordinate geometry to three Cs1+, one Ta5+, and one S+1.27- atom. The S–S bond length is 2.09 Å. In the ninth S+1.27- site, S+1.27- is bonded in a distorted single-bond geometry to four Cs1+ and one Ta5+ atom. In the tenth S+1.27- site, S+1.27- is bonded in a 5-coordinate geometry to two Cs1+, two Ta5+, and one S+1.27- atom. In the eleventh S+1.27- site, S+1.27- is bonded in a 2-coordinate geometry to two Cs1+, two Ta5+, and one S+1.27- atom.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Materials Data on Cs6K3AlSb4 by Materials Project

Cs6K3AlSb4 crystallizes in the hexagonal P6_3/mmc space group. The structure is three-dimensional. Cs1+ is bonded in a 3-coordinate geometry to four equivalent Cs1+, one K1+, and five Sb3- atoms. All Cs–Cs bond lengths are 4.17 Å. The Cs–K bond length is 3.85 Å. There are a spread of Cs–Sb bond distances ranging from 4.08–4.29 Å. K1+ is bonded in a 4-coordinate geometry to two equivalent Cs1+ and four Sb3- atoms. There are two shorter (3.64 Å) and two longer (3.73 Å) K–Sb bond lengths. Al3+ is bonded in a trigonal planar geometry to three equivalent Sb3- atoms. All Al–Sb bond lengths are 2.69 Å. There are two inequivalent Sb3- sites. In the first Sb3- site, Sb3- is bonded to six equivalent Cs1+ and six equivalent K1+ atoms to form face-sharing SbCs6K6 cuboctahedra. In the second Sb3- site, Sb3- is bonded in a 1-coordinate geometry to eight equivalent Cs1+, two equivalent K1+, and one Al3+ atom.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Materials Data on Cs4SnO4 by Materials Project

Cs4SnO4 crystallizes in the monoclinic P2_1/c space group. The structure is three-dimensional. there are four inequivalent Cs1+ sites. In the first Cs1+ site, Cs1+ is bonded to four O2- atoms to form distorted CsO4 tetrahedra that share corners with four equivalent SnO4 tetrahedra and an edgeedge with one CsO4 tetrahedra. There are a spread of Cs–O bond distances ranging from 2.92–2.99 Å. In the second Cs1+ site, Cs1+ is bonded in a 5-coordinate geometry to five O2- atoms. There are a spread of Cs–O bond distances ranging from 3.00–3.44 Å. In the third Cs1+ site, Cs1+ is bonded in a 4-coordinate geometry to five O2- atoms. There are a spread of Cs–O bond distances ranging from 2.89–3.64 Å. In the fourth Cs1+ site, Cs1+ is bonded in a 5-coordinate geometry to five O2- atoms. There are a spread of Cs–O bond distances ranging from 3.04–3.30 Å. Sn4+ is bonded to four O2- atoms to form SnO4 tetrahedra that share corners with four equivalent CsO4 tetrahedra. All Sn–O bond lengths are 2.01 Å. There are four inequivalent O2- sites. In the first O2- site, O2- is bonded in a 6-coordinate geometry to five Cs1+ and one Sn4+ atom. In the second O2- site, O2- is bonded in a 1-coordinate geometry to four Cs1+ and one Sn4+ atom. In the third O2- site, O2- is bonded in a 1-coordinate geometry to five Cs1+ and one Sn4+ atom. In the fourth O2- site, O2- is bonded in a 6-coordinate geometry to five Cs1+ and one Sn4+ atom.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Materials Data on Cs2In2Sb3 by Materials Project

Cs2In2Sb3 crystallizes in the monoclinic P2_1/c space group. The structure is three-dimensional. there are four inequivalent Cs1+ sites. In the first Cs1+ site, Cs1+ is bonded in a 2-coordinate geometry to six Sb+2.67- atoms. There are a spread of Cs–Sb bond distances ranging from 3.71–4.33 Å. In the second Cs1+ site, Cs1+ is bonded in a 7-coordinate geometry to seven Sb+2.67- atoms. There are a spread of Cs–Sb bond distances ranging from 3.91–4.45 Å. In the third Cs1+ site, Cs1+ is bonded in a 6-coordinate geometry to six Sb+2.67- atoms. There are a spread of Cs–Sb bond distances ranging from 3.77–4.30 Å. In the fourth Cs1+ site, Cs1+ is bonded in a hexagonal planar geometry to six Sb+2.67- atoms. There are a spread of Cs–Sb bond distances ranging from 3.79–4.18 Å. There are four inequivalent In3+ sites. In the first In3+ site, In3+ is bonded to four Sb+2.67- atoms to form a mixture of edge and corner-sharing InSb4 tetrahedra. There are a spread of In–Sb bond distances ranging from 2.93–2.99 Å. In the second In3+ site, In3+ is bonded to four Sb+2.67- atoms to form a mixture of edge and corner-sharing InSb4 tetrahedra. There are a spread of In–Sb bond distances ranging from 2.89–2.94 Å. In the third In3+ site, In3+ is bonded to four Sb+2.67- atoms to form a mixture of edge and corner-sharing InSb4 tetrahedra. There are a spread of In–Sb bond distances ranging from 2.91–2.93 Å. In the fourth In3+ site, In3+ is bonded to four Sb+2.67- atoms to form a mixture of edge and corner-sharing InSb4 tetrahedra. There are a spread of In–Sb bond distances ranging from 2.88–3.03 Å. There are six inequivalent Sb+2.67- sites. In the first Sb+2.67- site, Sb+2.67- is bonded to three Cs1+ and three In3+ atoms to form distorted edge-sharing SbCs3In3 pentagonal pyramids. In the second Sb+2.67- site, Sb+2.67- is bonded in a 7-coordinate geometry to four Cs1+, two In3+, and one Sb+2.67- atom. The Sb–Sb bond length is 2.89 Å. In the third Sb+2.67- site, Sb+2.67- is bonded in a 3-coordinate geometry to five Cs1+ and three In3+ atoms. In the fourth Sb+2.67- site, Sb+2.67- is bonded in a 7-coordinate geometry to four Cs1+, two In3+, and one Sb+2.67- atom. In the fifth Sb+2.67- site, Sb+2.67- is bonded in a 3-coordinate geometry to five Cs1+ and three In3+ atoms. In the sixth Sb+2.67- site, Sb+2.67- is bonded to four Cs1+ and three In3+ atoms to form distorted SbCs4In3 pentagonal bipyramids that share an edgeedge with one SbCs4In3 pentagonal bipyramid and edges with two equivalent SbCs3In3 pentagonal pyramids.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Materials Data on CsCd(NO2)3 by Materials Project

Cs(NO2)3Cd crystallizes in the cubic Pm-3 space group. The structure is three-dimensional and consists of one cadmium molecule and one Cs(NO2)3 framework. In the Cs(NO2)3 framework, Cs1+ is bonded to twelve equivalent O2- atoms to form edge-sharing CsO12 cuboctahedra. All Cs–O bond lengths are 3.56 Å. N3+ is bonded in a linear geometry to two equivalent O2- atoms. Both N–O bond lengths are 1.24 Å. O2- is bonded in a single-bond geometry to two equivalent Cs1+ and one N3+ atom.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Materials Data on CsEr6CI12 by Materials Project

CsEr6CI12 crystallizes in the trigonal R-3 space group. The structure is three-dimensional. Cs is bonded in a cuboctahedral geometry to twelve I atoms. There are six shorter (4.26 Å) and six longer (4.30 Å) Cs–I bond lengths. Er is bonded in a 6-coordinate geometry to one C and five I atoms. The Er–C bond length is 2.49 Å. There are a spread of Er–I bond distances ranging from 2.99–3.51 Å. C is bonded in an octahedral geometry to six equivalent Er atoms. There are two inequivalent I sites. In the first I site, I is bonded in a 3-coordinate geometry to one Cs and two equivalent Er atoms. In the second I site, I is bonded in a 4-coordinate geometry to one Cs and three equivalent Er atoms.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Materials Data on CsSbClF3 by Materials Project

CsSbClF3 crystallizes in the tetragonal I-42m space group. The structure is three-dimensional. there are two inequivalent Cs1+ sites. In the first Cs1+ site, Cs1+ is bonded in a 10-coordinate geometry to four equivalent Cl1- and six F1- atoms. All Cs–Cl bond lengths are 3.73 Å. There are two shorter (3.12 Å) and four longer (3.19 Å) Cs–F bond lengths. In the second Cs1+ site, Cs1+ is bonded in a 4-coordinate geometry to four equivalent Cl1- and eight F1- atoms. All Cs–Cl bond lengths are 3.67 Å. There are four shorter (3.20 Å) and four longer (3.62 Å) Cs–F bond lengths. Sb3+ is bonded in a 5-coordinate geometry to two equivalent Cl1- and three F1- atoms. Both Sb–Cl bond lengths are 2.93 Å. There is one shorter (1.97 Å) and two longer (2.01 Å) Sb–F bond length. Cl1- is bonded to four Cs1+, two equivalent Sb3+, and two equivalent F1- atoms to form a mixture of distorted edge, face, and corner-sharing ClCs4Sb2F2 hexagonal bipyramids. Both Cl–F bond lengths are 3.23 Å. There are two inequivalent F1- sites. In the first F1- site, F1- is bonded in a distorted single-bond geometry to two Cs1+ and one Sb3+ atom. In the second F1- site, F1- is bonded in a distorted single-bond geometry to three Cs1+, one Sb3+, and two equivalent Cl1- atoms.

36 MATERIALS SCIENCE↗
DOE OSTI2020

Materials Data on Cs3Np(Cl2O)2 by Materials Project

Cs3NpO2Cl4 crystallizes in the monoclinic C2/c space group. The structure is three-dimensional. there are two inequivalent Cs1+ sites. In the first Cs1+ site, Cs1+ is bonded in a 8-coordinate geometry to two equivalent O2- and six Cl1- atoms. There are one shorter (3.22 Å) and one longer (3.23 Å) Cs–O bond lengths. There are a spread of Cs–Cl bond distances ranging from 3.56–3.90 Å. In the second Cs1+ site, Cs1+ is bonded in a 8-coordinate geometry to two equivalent O2- and six Cl1- atoms. Both Cs–O bond lengths are 3.12 Å. There are a spread of Cs–Cl bond distances ranging from 3.50–3.99 Å. Np5+ is bonded in a distorted linear geometry to two equivalent O2- and four Cl1- atoms. Both Np–O bond lengths are 1.85 Å. All Np–Cl bond lengths are 2.78 Å. O2- is bonded in a distorted single-bond geometry to three Cs1+ and one Np5+ atom. There are two inequivalent Cl1- sites. In the first Cl1- site, Cl1- is bonded in a 5-coordinate geometry to four Cs1+ and one Np5+ atom. In the second Cl1- site, Cl1- is bonded in a 1-coordinate geometry to five Cs1+ and one Np5+ atom.

36 MATERIALS SCIENCE↗