SEARCH · Engineering Papers
Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.
SrBBi is half-Heusler structured and crystallizes in the cubic F-43m space group. The structure is zero-dimensional and consists of four bismuth molecules, four boron molecules, and four strontium molecules.
Sr(NH2)2 crystallizes in the monoclinic P2_1/c space group. The structure is zero-dimensional and consists of four strontium;azanide molecules. Sr2+ is bonded in a 2-coordinate geometry to two N3- atoms. There are one shorter (2.62 Å) and one longer (2.63 Å) Sr–N bond lengths. There are two inequivalent N3- sites. In the first N3- site, N3- is bonded in a distorted water-like geometry to one Sr2+ and two H1+ atoms. Both N–H bond lengths are 1.03 Å. In the second N3- site, N3- is bonded in a distorted water-like geometry to one Sr2+ and two H1+ atoms. Both N–H bond lengths are 1.03 Å. There are four inequivalent H1+ sites. In the first H1+ site, H1+ is bonded in a single-bond geometry to one N3- atom. In the second H1+ site, H1+ is bonded in a single-bond geometry to one N3- atom. In the third H1+ site, H1+ is bonded in a single-bond geometry to one N3- atom. In the fourth H1+ site, H1+ is bonded in a single-bond geometry to one N3- atom.
Sr(SrNd5Al6Si9(N2O)9)2 is Chalcostibite-derived structured and crystallizes in the monoclinic Cm space group. The structure is three-dimensional and consists of two strontium molecules and one SrNd5Al6Si9(N2O)9 framework. In the SrNd5Al6Si9(N2O)9 framework, Sr is bonded in a 5-coordinate geometry to five N and five O atoms. There are a spread of Sr–N bond distances ranging from 2.60–3.08 Å. There are a spread of Sr–O bond distances ranging from 2.65–3.08 Å. There are six inequivalent Nd sites. In the first Nd site, Nd is bonded in a 5-coordinate geometry to five N and five O atoms. There are a spread of Nd–N bond distances ranging from 2.50–3.09 Å. There are a spread of Nd–O bond distances ranging from 2.46–3.12 Å. In the second Nd site, Nd is bonded in a 5-coordinate geometry to five N and five O atoms. There are a spread of Nd–N bond distances ranging from 2.49–3.12 Å. There are a spread of Nd–O bond distances ranging from 2.39–3.19 Å. In the third Nd site, Nd is bonded in a 5-coordinate geometry to five N and five O atoms. There are a spread of Nd–N bond distances ranging from 2.51–3.10 Å. There are a spread of Nd–O bond distances ranging from 2.40–3.15 Å. In the fourth Nd site, Nd is bonded in a 5-coordinate geometry to five N and five O atoms. There are a spread of Nd–N bond distances ranging from 2.50–3.11 Å. There are a spread of Nd–O bond distances ranging from 2.41–3.19 Å. In the fifth Nd site, Nd is bonded in a 5-coordinate geometry to five N and five O atoms. There are a spread of Nd–N bond distances ranging from 2.52–3.10 Å. There are a spread of Nd–O bond distances ranging from 2.42–3.14 Å. In the sixth Nd site, Nd is bonded in a 5-coordinate geometry to five N and five O atoms. There are a spread of Nd–N bond distances ranging from 2.51–3.08 Å. There are a spread of Nd–O bond distances ranging from 2.38–3.14 Å. There are seven inequivalent Al sites. In the first Al site, Al is bonded to three N and one O atom to form AlN3O tetrahedra that share corners with two AlN3O tetrahedra and corners with five SiN4 tetrahedra. There is two shorter (1.83 Å) and one longer (1.88 Å) Al–N bond length. The Al–O bond length is 1.80 Å. In the second Al site, Al is bonded to three N and one O atom to form AlN3O tetrahedra that share corners with two AlN3O tetrahedra and corners with five SiN4 tetrahedra. There is two shorter (1.83 Å) and one longer (1.89 Å) Al–N bond length. The Al–O bond length is 1.80 Å. In the third Al site, Al is bonded to three N and one O atom to form AlN3O tetrahedra that share corners with two equivalent AlN3O tetrahedra and corners with five SiN4 tetrahedra. There is two shorter (1.83 Å) and one longer (1.88 Å) Al–N bond length. The Al–O bond length is 1.80 Å. In the fourth Al site, Al is bonded to three N and one O atom to form AlN3O tetrahedra that share corners with two AlN3O tetrahedra and corners with five SiN4 tetrahedra. There is two shorter (1.83 Å) and one longer (1.88 Å) Al–N bond length. The Al–O bond length is 1.79 Å. In the fifth Al site, Al is bonded to three N and one O atom to form AlN3O tetrahedra that share corners with two equivalent AlN3O tetrahedra and corners with five SiN3O tetrahedra. There is two shorter (1.83 Å) and one longer (1.88 Å) Al–N bond length. The Al–O bond length is 1.80 Å. In the sixth Al site, Al is bonded to three N and one O atom to form AlN3O tetrahedra that share corners with two AlN3O tetrahedra and corners with five SiN4 tetrahedra. There are a spread of Al–N bond distances ranging from 1.83–1.89 Å. The Al–O bond length is 1.80 Å. In the seventh Al site, Al is bonded to three N and one O atom to form AlN3O tetrahedra that share corners with two AlN3O tetrahedra and corners with five SiN4 tetrahedra. There are a spread of Al–N bond distances ranging from 1.83–1.87 Å. The Al–O bond length is 1.78 Å. There are eleven inequivalent Si sites. In the first Si site, Si is bonded to four N atoms to form SiN4 tetrahedra that share corners with two SiN3O tetrahedra and corners with four AlN3O tetrahedra. There are a spread of Si–N bond distances ranging from 1.72–1.74 Å. In the second Si site, Si is bonded to three N and one O atom to form SiN3O tetrahedra that share corners with three AlN3O tetrahedra and corners with three SiN4 tetrahedra. There is one shorter (1.74 Å) and two longer (1.75 Å) Si–N bond length. The Si–O bond length is 1.66 Å. In the third Si site, Si is bonded to three N and one O atom to form SiN3O tetrahedra that share corners with three AlN3O tetrahedra and corners with three SiN4 tetrahedra. There is two shorter (1.74 Å) and one longer (1.75 Å) Si–N bond length. The Si–O bond length is 1.66 Å. In the fourth Si site, Si is bonded to four N atoms to form SiN4 tetrahedra that share corners with two SiN3O tetrahedra and corners with four AlN3O tetrahedra. There is three shorter (1.72 Å) and one longer (1.74 Å) Si–N bond length. In the fifth Si site, Si is bonded to three N and one O atom to form SiN3O tetrahedra that share corners with three AlN3O tetrahedra and corners with three SiN3O tetrahedra. There is one shorter (1.73 Å) and two longer (1.75 Å) Si–N bond length. The Si–O bond length is 1.66 Å. In the sixth Si site, Si is bonded to three N and one O atom to form SiN3O tetrahedra that share corners with three AlN3O tetrahedra and corners with three SiN4 tetrahedra. There is one shorter (1.73 Å) and two longer (1.75 Å) Si–N bond length. The Si–O bond length is 1.66 Å. In the seventh Si site, Si is bonded to three N and one O atom to form SiN3O tetrahedra that share corners with three AlN3O tetrahedra and corners with three SiN4 tetrahedra. There is one shorter (1.73 Å) and two longer (1.75 Å) Si–N bond length. The Si–O bond length is 1.67 Å. In the eighth Si site, Si is bonded to three N and one O atom to form SiN3O tetrahedra that share corners with three AlN3O tetrahedra and corners with three SiN3O tetrahedra. There is one shorter (1.73 Å) and two longer (1.76 Å) Si–N bond length. The Si–O bond length is 1.65 Å. In the ninth Si site, Si is bonded to three N and one O atom to form SiN3O tetrahedra that share corners with three AlN3O tetrahedra and corners with three SiN4 tetrahedra. There is two shorter (1.73 Å) and one longer (1.76 Å) Si–N bond length. The Si–O bond length is 1.67 Å. In the tenth Si site, Si is bonded to four N atoms to form SiN4 tetrahedra that share corners with two SiN3O tetrahedra and corners with four AlN3O tetrahedra. There is two shorter (1.72 Å) and two longer (1.74 Å) Si–N bond length. In the eleventh Si site, Si is bonded to four N atoms to form SiN4 tetrahedra that share corners with two equivalent SiN3O tetrahedra and corners with four AlN3O tetrahedra. There is two shorter (1.72 Å) and two longer (1.74 Å) Si–N bond length. There are twenty-one inequivalent N sites. In the first N site, N is bonded in a trigonal planar geometry to one Nd, two Al, and one Si atom. In the second N site, N is bonded in a 2-coordinate geometry to three Nd and two Si atoms. In the third N site, N is bonded in a 2-coordinate geometry to three Nd and two Si atoms. In the fourth N site, N is bonded in a trigonal planar geometry to one Nd, two Al, and one Si atom. In the fifth N site, N is bonded to one Nd, one Al, and two Si atoms to form distorted NNdAlSi2 tetrahedra that share a cornercorner with one NNdAlSi2 tetrahedra, corners with two OSrNd3 tetrahedra, and a cornercorner with one NSrAlSi2 trigonal pyramid. In the sixth N site, N is bonded in a trigonal planar geometry to one Nd, two equivalent Al, and one Si atom. In the seventh N site, N is bonded in a 2-coordinate geometry to one Sr, two Nd, and two Si atoms. In the eighth N site, N is bonded to one Nd, one Al, and two Si atoms to form distorted NNdAlSi2 trigonal pyramids that share corners with two OSrNd3 tetrahedra and corners with two NNdAlSi2 trigonal pyramids. In the ninth N site, N is bonded in a trigonal planar geometry to one Nd, two Al, and one Si atom. In the tenth N site, N is bonded to one Nd, one Al, and two equivalent Si atoms to form distorted NNdAlSi2 trigonal pyramids that share corners with two equivalent ONd4 tetrahedra. In the eleventh N site, N is bonded in a 2-coordinate geometry to one Sr, two Nd, and two Si atoms. In the twelfth N site, N is bonded in a trigonal planar geometry to one Nd, two Al, and one Si atom. In the thirteenth N site, N is bonded in a 2-coordinate geometry to three Nd and two Si atoms. In the fourteenth N site, N is bonded in a 4-coordinate geometry to one Nd, one Al, and two Si atoms. In the fifteenth N site, N is bonded in a trigonal planar geometry to one Sr, two Al, and one Si atom. In the sixteenth N site, N is bonded to one Nd, one Al, and two equivalent Si atoms to form distorted NNdAlSi2 trigonal pyramids that share corners with two equivalent OSrNd3 tetrahedra and corners with two equivalent NNdAlSi2 trigonal pyramids. In the seventeenth N site, N is bonded in a 2-coordinate geometry to one Sr, two Nd, and two Si atoms. In the eighteenth N site, N is bonded in a 2-coordinate geometry to three Nd and two Si atoms. In the nineteenth N site, N is bonded to one Nd, one Al, and two Si atoms to form distorted NNdAlSi2 tetrahedra that share a cornercorner with one NNdAlSi2 tetrahedra, corners with two OSrNd3 tetrahedra, and a cornercorner with one NSrAlSi2 trigonal pyramid. In the twentieth N site, N is bonded in a trigonal planar geometry to one Nd, two equivalent Al, and one Si atom. In the twenty-first N site, N is bonded to one Sr, one Al, and two Si atoms to form distorted NSrAlSi2 trigonal pyramids that share corners with two NNdAlSi2 tetrahedra and corners with two OSrNd3 tetrahedra. There are ten inequivalent O sites. In the first O site, O is bonded to four Nd atoms to form distorted ONd4 tetrahedra that share corners with two NNdAlSi2 tetrahedra, corners with four OSrNd3 tetrahedra, and corners with two NNdAlSi2 trigonal pyramids. In the second O site, O is bonded in a 2-coordinate geometry to three Nd, one Al, and one Si atom. In the third O site, O is bonded in a 2-coordinate geometry to three Nd, one Al, and one Si atom. In the fourth O site, O is bonded in a 2-coordinate geometry to three Nd, one Al, and one Si atom. In the fifth O site, O is bonded to one Sr and three Nd atoms to form distorted OSrNd3 tetrahedra that share a cornercorner with one NNdAlSi2 tetrahedra, corners with four OSrNd3 tetrahedra, and corners with two NNdAlSi2 trigonal pyramids. In the sixth O site, O is bonded in a 2-coordinate geometry to one Sr, two Nd, one Al, and one Si atom. In the seventh O site, O is bonded in a 2-coordinate geometry to three Nd, one Al, and one Si atom. In the eighth O site, O is bonded in a 2-coordinate geometry to one Sr, two Nd, one Al, and one Si atom. In the ninth O site, O is bonded to one Sr and three Nd atoms to form distorted OSrNd3 tetrahedra that share a cornercorner with one NNdAlSi2 tetrahedra, corners with four OSrNd3 tetrahedra, and corners with two NNdAlSi2 trigonal pyramids. In the tenth O site, O is bonded in a 2-coordinate geometry to one Sr, two Nd, one Al, and one Si atom.
SrCoO crystallizes in the orthorhombic Cmcm space group. The structure is one-dimensional and consists of four strontium molecules and two CoO ribbons oriented in the (0, 0, 1) direction. In each CoO ribbon, Co is bonded in a linear geometry to two equivalent O atoms. Both Co–O bond lengths are 1.75 Å. O is bonded in a linear geometry to two equivalent Co atoms.
SrSr3As8F48 crystallizes in the cubic P-43m space group. The structure is three-dimensional and consists of one strontium molecule and one Sr3As8F48 framework. In the Sr3As8F48 framework, Sr2+ is bonded to eight F1- atoms to form distorted SrF8 hexagonal bipyramids that share corners with eight AsF6 octahedra. The corner-sharing octahedra tilt angles range from 29–30°. All Sr–F bond lengths are 2.65 Å. There are two inequivalent As5+ sites. In the first As5+ site, As5+ is bonded to six F1- atoms to form AsF6 octahedra that share corners with three equivalent SrF8 hexagonal bipyramids. There is three shorter (1.73 Å) and three longer (1.83 Å) As–F bond length. In the second As5+ site, As5+ is bonded to six F1- atoms to form AsF6 octahedra that share corners with three equivalent SrF8 hexagonal bipyramids. There is three shorter (1.73 Å) and three longer (1.83 Å) As–F bond length. There are four inequivalent F1- sites. In the first F1- site, F1- is bonded in a distorted single-bond geometry to one Sr2+ and one As5+ atom. In the second F1- site, F1- is bonded in a distorted single-bond geometry to one Sr2+ and one As5+ atom. In the third F1- site, F1- is bonded in a single-bond geometry to one As5+ atom. In the fourth F1- site, F1- is bonded in a single-bond geometry to one As5+ atom.
SrLi2Si is Cyanogen Chloride-like structured and crystallizes in the orthorhombic Immm space group. The structure is zero-dimensional and consists of two strontium molecules and two Li2Si clusters. In each Li2Si cluster, Li1+ is bonded in a single-bond geometry to one Si4- atom. The Li–Si bond length is 2.45 Å. Si4- is bonded in a linear geometry to two equivalent Li1+ atoms.
SrSr3(AuF6)8 crystallizes in the cubic P-43m space group. The structure is three-dimensional and consists of one strontium molecule and one Sr3(AuF6)8 framework. In the Sr3(AuF6)8 framework, Sr2+ is bonded to eight F1- atoms to form distorted SrF8 hexagonal bipyramids that share corners with eight AuF6 octahedra. The corner-sharing octahedra tilt angles range from 27–29°. There are four shorter (2.65 Å) and four longer (2.66 Å) Sr–F bond lengths. There are two inequivalent Au5+ sites. In the first Au5+ site, Au5+ is bonded to six F1- atoms to form AuF6 octahedra that share corners with three equivalent SrF8 hexagonal bipyramids. There is three shorter (1.91 Å) and three longer (1.98 Å) Au–F bond length. In the second Au5+ site, Au5+ is bonded to six F1- atoms to form AuF6 octahedra that share corners with three equivalent SrF8 hexagonal bipyramids. There is three shorter (1.91 Å) and three longer (1.98 Å) Au–F bond length. There are four inequivalent F1- sites. In the first F1- site, F1- is bonded in a distorted bent 150 degrees geometry to one Sr2+ and one Au5+ atom. In the second F1- site, F1- is bonded in a distorted bent 150 degrees geometry to one Sr2+ and one Au5+ atom. In the third F1- site, F1- is bonded in a single-bond geometry to one Au5+ atom. In the fourth F1- site, F1- is bonded in a single-bond geometry to one Au5+ atom.
Sr(PdSi)6 crystallizes in the orthorhombic Ibam space group. The structure is three-dimensional and consists of four strontium molecules and one PdSi framework. In the PdSi framework, there are two inequivalent Pd+2.33+ sites. In the first Pd+2.33+ site, Pd+2.33+ is bonded in a 5-coordinate geometry to five Si+2.67- atoms. There are a spread of Pd–Si bond distances ranging from 2.45–2.62 Å. In the second Pd+2.33+ site, Pd+2.33+ is bonded in a 7-coordinate geometry to seven Si+2.67- atoms. There are a spread of Pd–Si bond distances ranging from 2.44–2.98 Å. There are two inequivalent Si+2.67- sites. In the first Si+2.67- site, Si+2.67- is bonded in a 5-coordinate geometry to six Pd+2.33+ atoms. In the second Si+2.67- site, Si+2.67- is bonded in a 4-coordinate geometry to five Pd+2.33+ atoms.
SrRuO3 crystallizes in the orthorhombic Pnma space group. The structure is zero-dimensional and consists of four hydrogen peroxide molecules, four ruthenium molecules, four strontium molecules, and four water molecules.
(Sr)6H2 is Uranium Silicide-like structured and crystallizes in the hexagonal P6_3/mmc space group. The structure is zero-dimensional and consists of two dihydrogen molecules and six strontium, elemental molecules.
The overall goals of the program were: • To understand the microstructural basis of long-term performance loss in solid oxide fuel cells (SOFCs) with cathodes based on lanthanum strontium manganite (LSM, (La 1–x Sr x ) 1–yM nO 3±z ); • To develop strategies for optimizing LSM–based cathodes that achieve improved long-term performance, while exhibiting microstructural and chemical stability, for commercial fuel cell systems. The research project carried out accelerated testing of SOFCs with LSM-based cathodes of selected compositions. After intervals of accelerated testing (and control tests using non-accelerated conditions), the cells underwent extensive microstructural characterization to determine the physical and chemical changes in the cells. By analysis of a) the results of the testing, b) the observed microstructural changes, and c) the differences in these correlations between different cathode compositions and test durations, the research: • Identified a correlation between microstructural change and performance loss: specifically, between decrease of three-phase boundary (TPB) density and increase of area specific re-sistance (ASR) during operation; • Identified a cathode composition parameter — Mn excess, defined as 1/(1–y) in (La 1–x Sr x ) 1–y MnO 3±z ) — and how it affects TPB density, ASR and change of cell performance over time.
The Tank Closure Cesium Removal (TCCR) system uses ion exchange columns filled with crystalline silicotitanate (CST) media to process radioactive waste solutions for the removal of ¹³⁷Cs. TCCR currently focuses on dissolving Savannah River Site (SRS) radioactive tank waste (primarily sodium saltcake solids) within Tank 10H followed by at-tank ion exchange column treatment. Two supernate batches from Tank 10H have been processed through the TCCR unit and processing of a third batch is expected soon. After processing of this supernate batch, plans are to replace the CST columns and process dissolved salt solution from Tank 9H through Tank 10H and then through the new CST columns installed in the TCCR unit. The new columns are expected to contain either a media similar to an archived CST batch (IE-911) or the R9120-B CST media used in the current TCCR columns (the two materials are fundamentally the same; just different specifications, product names, and preconditioning steps). Samples of Tank 9H dissolved saltcake were received at the Savannah River National Laboratory (SRNL) and characterized. The Tank 9H supernate contained a high sodium concentration (~9.6 M Na⁺) and will require dilution to near 6 M [Na⁺] prior to processing through the TCCR unit. The cesium concentration in Tank 9H is currently significantly higher than was observed with Tank 10H. Three dilutions of the Tank 9H supernate were conducted to mimic possible dilutions that could be conducted in the tank farm prior to TCCR processing using inhibited water, sodium hydroxide, and sodium nitrate solutions. Dilution #1 was prepared by diluting the Tank 9H supernate by a factor of 1.6 with inhibited water, Dilution #2 was prepared by diluting the Tank 9H supernate by a factor of 3.7 with a mixed sodium hydroxide/sodium nitrate diluent, and Dilution #3 was prepared by also diluting by a factor of 3.7 but with sodium hydroxide only. All three dilutions have similar Na⁺ concentrations (~6 M), but Dilutions #2 and #3 contain significantly less cesium. Major and key minor components of the diluted Tank 9H supernate samples are provided in Table ES-1. Batch contact equilibrium tests were conducted with the Tank 9H dilutions and the two different CST media batches being considered for use in the new TCCR columns. Results are summarized in Table ES-2 and compared to ZAM model predictions. The highest cesium distribution coefficient and percent removal were observed with Dilution #3. IE-911 CST (an archived CST media batch) was more effective at removing cesium than the more recently prepared R9120-B CST media, though both media samples removed >88% of the cesium and the differences may not be statistically different considering the overall uncertainty. Based on the results, maximum cesium loadings were calculated for each CST media type and Tank 9H dilution. In general, maximum cesium loadings from dilutions of this supernate batch are quite high (approaching 0.1 mmol total Cs⁺/g CST for Dilution #1). The highest calculated maximum ¹³⁷Cs loading for the Tank 9H dilutions using the ZAM model with input of the tank compositions and batch contact results was 207 Ci/kg CST (Dilution #1 with IE-911 CST). In all cases, higher maximum cesium loading values were predicted for IE-911 CST versus R9120-B, although the differences varied considerably between the dilutions. The maximum loading value for IE-911 CST with Tank 9H Dilution #1 was only 7% higher than the maximum loading for R9120-B. The maximum loading value for IE-911 CST with Dilution #3 was 24% higher than the maximum loading for R9120-B. Dilution #2 was intermediate between these values. Note that these maximum loading values are the theoretical calculated values, and actual operating conditions will cause differences. A CST binder dilution (correction) factor near 0.7 (relative to pure powder CST) was required for each batch contact test with IE-911 engineered CST using the three Tank 9H dilutions. Correction factors calculated for R9120-B CST ranged from 0.56 to 0.66 for the three dilutions. Following the batch contact tests, the CST samples were isolated from the Tank 9H solution, washed, dried, and digested in acid following established procedures. The analysis results are provided in Table ES-3. Total cesium loading values determined by CST digestion were similar to the calculated loading values based on solution analysis (Table ES-2) for all samples. In addition, the CST was observed to load calcium (R9120-B sample only), iron, strontium, lead, uranium, and plutonium after contact with the waste supernate, as has been observed previously.
There are three Atom Sources within the MAGIS-100 experiment, located at the ends and midpoint of the shaft, adjacent to the vacuum tube. Each Atom Source weighs approximately 700 pounds and contains the optical components for the atom interferometry and delivers the Strontium.
The objective of this work is to adapt ambient ionization mass spectrometry (AMS) techniques for the rapid analysis of intact uranium complexes, stable strontium, cerium, and explosive compounds. The methods used were “soft ionization” techniques, which facilitate the detection of whole molecule complexes. The soft ionization mass spectrometry (MS) techniques that were investigated include paper spray ionization (PSI), matrix-assisted ionization (MAI), electrospray ionization (ESI) and direct analysis in real time (DART). For the first time, PSI-MS methods were successfully developed for whole molecule uranium-containing analytes (uranyl acetate, uranyl nitrate, and uranyl-tributylphosphate complexes). This was also the first demonstration of uranium complex detection and characterization and one of the few examples of inorganic analysis using MAI techniques. Proof of concept experiments also putatively identified matrix-derived ions and ion complexes that have not previously been described in the literature. Additionally, PSI-MS on cotton swipe samples doped with a multi-element standard containing μg levels of U, Bi, Pb, Cd, Fe, and Zn were directly analyzed without purification, representing a major improvement over existing methods. Both PSI and MAI methods demonstrated limits of detection (LODs) in the 10 - 100’s ng for various uranyl species within a range of 10’s ppm - 100’s ppb, dependent on analytical method and analyte species. AMS methods were also developed for other inorganics, including Ce and Sr, and organic explosive residues to address specific challenges in environmental monitoring and forensics. Further refinement and qualification of the AMS techniques developed within this effort would lead to significant cost reduction and timeliness by facilitating the triage and queueing of samples for subsequent more sensitive and time-consuming analyses.
The objectives of the vadose modeling for the updated Hanford Site composite analysis (CA) are to simulate the flow and transport of water and radionuclide releases from the surface to the water table and to provide radionuclide transfer rates for the plateau to river (P2R) model, version 8.3 (CP-57037, Model Package Report: Plateau to River Groundwater Model, Version 8.3). Water additions include natural recharge and water discharged to the ground as a result of industrial processes associated with Hanford Site operations. Contaminant sources include radionuclides in water discharged to the ground during operations and radionuclides disposed “dry” in solid waste burial grounds or other means. The following 16 radionuclides were selected for this modeling effort; carbon-14 (C-14), chlorine-36 (Cl-36), tritium (H-3), iodine-129 (I-129), neptunium-237 (Np-237), rhenium-187 (Re-187), strontium-90 (Sr-90), technetium-99 (Tc-99), uranium-232 (U-232), uranium-233 (U-233), uranium-234 (U-234), uranium-235 (U-235), uranium-236 (U-236), uranium-238 (U-238), radium-226 (Ra-226), and thorium-230 (Th-230). The simulation time starts in 1943 and ends at 12070, which is 10,000 years after assumed Hanford Site closure in 2070. The parallel version of the Subsurface Transport Over Multiple Phases (STOMP1) simulator, officially named the exascale Subsurface Transport Over Multiple Phases (eSTOMP), is used to simulate flow and transport for the vadose models. The documentation for the STOMP code is comprehensive. The theoretical and numerical approaches applied in the STOMP code are documented in a published theory guide (PNNL-12030, STOMP Subsurface Transport Over Multiple Phases Version 2.0 Theory Guide). The code has undergone a rigorous verification procedure against analytical solutions, laboratory-scale experiments, and field-scale demonstrations. The application guide (PNNL-11216, STOMP Subsurface Transport Over Multiple Phases Application Guide) provides instructive examples in the application of the code to classical groundwater problems. The user’s guide (PNNL-15782, STOMP: Subsurface Transport Over Multiple Phases Version 4.0: User’s Guide) describes the general use, input file formatting, compilation, and execution of the code. The primary output of the vadose zone modeling is radionuclide transfer rates to the groundwater for input into the P2R model. The rates will be summed over the 100 by 100 m P2R grid cells that fall within the vadose zone model source domain.
The objectives of the vadose modeling for the updated Hanford Site composite analysis (CA) are to simulate the flow and transport of water and radionuclide releases from the surface to the water table and to provide radionuclide transfer rates for the plateau to river (P2R) model, version 8.3 (CP-57037, Model Package Report: Plateau to River Groundwater Model, Version 8.3). Water additions include natural recharge and water discharged to the ground as a result of industrial processes associated with Hanford Site operations. Contaminant sources include radionuclides in water discharged to the ground during operations and radionuclides disposed “dry” in solid waste burial grounds or other means. The following 16 radionuclides were selected for this modeling effort: carbon-14 (C-14), chlorine-36 (Cl-36), tritium (H-3), iodine-129 (I-129), neptunium-237 (Np-237), rhenium-187 (Re-187), strontium-90 (Sr-90), technetium-99 (Tc-99), uranium-232 (U-232), uranium-233 (U-233), uranium-234 (U-234), uranium-235 (U-235), uranium-236 (U-236), uranium-238 (U-238), radium-226 (Ra-226), and thorium-230 (Th-230). The simulation time starts in 1943 and ends at 12070, which is 10,000 years after assumed Hanford Site closure in 2070. The parallel version of the Subsurface Transport Over Multiple Phases (STOMP1) simulator, officially named the exascale Subsurface Transport Over Multiple Phases (eSTOMP), is used to simulate flow and transport for the vadose models. The documentation for the STOMP code is comprehensive. The theoretical and numerical approaches applied in the STOMP code are documented in a published theory guide (PNNL-12030, STOMP Subsurface Transport Over Multiple Phases Version 2.0 Theory Guide). The code has undergone a rigorous verification procedure against analytical solutions, laboratory-scale experiments, and field-scale demonstrations. The application guide (PNNL-11216, STOMP Subsurface Transport Over Multiple Phases Application Guide) provides instructive examples in the application of the code to classical groundwater problems. The user’s guide (PNNL-15782, STOMP: Subsurface Transport Over Multiple Phases Version 4.0: User’s Guide) describes the general use, input file formatting, compilation, and execution of the code. The primary output of the vadose zone modeling is radionuclide transfer rates to the groundwater for input into the P2R model. The rates will be summed over the 100 by 100 m P2R grid cells that fall within the vadose zone model source domain.
The objectives of the vadose modeling for the updated Hanford Site composite analysis (CA) are to simulate the flow and transport of water and radionuclide releases from the surface to the water table and to provide radionuclide transfer rates for the plateau to river (P2R) model, version 8.3 (CP-57037, Model Package Report: Plateau to River Groundwater Model, Version 8.3). Water additions include natural recharge and water discharged to the ground as a result of industrial processes associated with Hanford Site operations. Contaminant sources include radionuclides in water discharged to the ground during operations and radionuclides disposed “dry” in solid waste burial grounds or other means. The following 16 radionuclides were selected for this modeling effort: carbon-14 (C-14), chlorine-36 (Cl-36), tritium (H-3), iodine-129 (I-129), neptunium-237 (Np-237), rhenium-187 (Re-187), strontium-90 (Sr-90), technetium-99 (Tc-99), uranium-232 (U-232), uranium-233 (U-233), uranium-234 (U-234), uranium-235 (U-235), uranium-236 (U-236), uranium-238 (U-238), radium-226 (Ra-226), and thorium-230 (Th-230). The simulation time starts in 1943 and ends at 12070, which is 10,000 years after assumed Hanford Site closure in 2070. The parallel version of the Subsurface Transport Over Multiple Phases (STOMP1) simulator, officially named the exascale Subsurface Transport Over Multiple Phases (eSTOMP), is used to simulate flow and transport for the vadose models. The documentation for the STOMP code is comprehensive. The theoretical and numerical approaches applied in the STOMP code are documented in a published theory guide (PNNL-12030, STOMP Subsurface Transport Over Multiple Phases Version 2.0 Theory Guide). The code has undergone a rigorous verification procedure against analytical solutions, laboratory-scale experiments, and field-scale demonstrations. The application guide (PNNL-11216, STOMP Subsurface Transport Over Multiple Phases Application Guide) provides instructive examples in the application of the code to classical groundwater problems. The user’s guide (PNNL-15782, STOMP: Subsurface Transport Over Multiple Phases Version 4.0: User’s Guide) describes the general use, input file formatting, compilation, and execution of the code. The primary output of the vadose zone modeling is radionuclide transfer rates to the groundwater for input into the P2R model. The rates will be summed over the 100 by 100 m P2R grid cells that fall within the vadose zone model source domain.
The objectives of the vadose modeling for the updated Hanford Site composite analysis (CA) are to simulate the flow and transport of water and radionuclide releases from the surface to the water table and to provide radionuclide transfer rates for the plateau to river (P2R) model, version 8.3 (CP-57037, Model Package Report: Plateau to River Groundwater Model, Version 8.3). Water additions include natural recharge and water discharged to the ground as a result of industrial processes associated with Hanford Site operations. Contaminant sources include radionuclides in water discharged to the ground during operations and radionuclides disposed “dry” in solid waste burial grounds or other means. The following 16 radionuclides were selected for this modeling effort: carbon-14 (C-14), chlorine-36 (Cl-36), tritium (H-3), iodine-129 (I-129), neptunium-237 (Np-237), rhenium-187 (Re-187), strontium-90 (Sr-90), technetium-99 (Tc-99), uranium-232 (U-232), uranium-233 (U-233), uranium-234 (U-234), uranium-235 (U-235), uranium-236 (U-236), uranium-238 (U-238), radium-226 (Ra-226), and thorium-230 (Th-230). The simulation time starts in 1943 and ends at 12070, which is 10,000 years after assumed Hanford Site closure in 2070. The parallel version of the Subsurface Transport Over Multiple Phases (STOMP1) simulator, officially named the exascale Subsurface Transport Over Multiple Phases (eSTOMP), is used to simulate flow and transport for the vadose models. The documentation for the STOMP code is comprehensive. The theoretical and numerical approaches applied in the STOMP code are documented in a published theory guide (PNNL-12030, STOMP Subsurface Transport Over Multiple Phases Version 2.0 Theory Guide). The code has undergone a rigorous verification procedure against analytical solutions, laboratory-scale experiments, and field-scale demonstrations. The application guide (PNNL-11216, STOMP Subsurface Transport Over Multiple Phases Application Guide) provides instructive examples in the application of the code to classical groundwater problems. The user’s guide (PNNL-15782, STOMP: Subsurface Transport Over Multiple Phases Version 4.0: User’s Guide) describes the general use, input file formatting, compilation, and execution of the code. The primary output of the vadose zone modeling is radionuclide transfer rates to the groundwater for input into the P2R model. The rates will be summed over the 100 by 100 m P2R grid cells that fall within the vadose zone model source domain.