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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.

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At least 37 records · Page 2
All sourcesNASA NTRSDOE OSTI
DOE OSTI2023

Measurement of isotopic separation of argon with the prototype of the cryogenic distillation plant Aria for dark matter searches

The Aria cryogenic distillation plant, located in Sardinia, Italy, is a key component of the DarkSide-20k experimental program for WIMP dark matter searches at the INFN Laboratori Nazionali del Gran Sasso, Italy. Aria is designed to purify the argon, extracted from underground wells in Colorado, USA, and used as the DarkSide-20k target material, to detector-grade quality. In this paper, we report the first measurement of argon isotopic separation by distillation with the 26 m tall Aria prototype. We discuss the measurement of the operating parameters of the column and the observation of the simultaneous separation of the three stable argon isotopes: ${}^{36}\hbox {Ar}$, ${}^{38}\textrm{Ar}$, and ${}^{40}\textrm{Ar}$. We also provide a detailed comparison of the experimental results with commercial process simulation software. This measurement of isotopic separation of argon is a significant achievement for the project, building on the success of the initial demonstration of isotopic separation of nitrogen using the same equipment in 2019.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2013

Implications of Plutonium isotopic separation on closed fuel cycles and repository design

Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation. This would have large impacts on LWR closed fuel cycles and waste management. If Pu-240 is removed before recycling plutonium as mixed oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, Americium, and Curium. Pu-240 is a fertile material and thus can be replaced by U-238. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Eliminating fertile Pu-240 and Pu-242 reduces the plutonium content in MOX fuel and simplifies fabrication. Reducing production of Pu-241 reduces production of Am-241 - the primary heat generator in spent nuclear fuels after several decades. Reducing heat generating Am-241 would reduce repository cost and waste toxicity. Avoiding Am- 241 avoids its decay product Np-237, a nuclide that partly controls long-term oxidizing repository performance. Most of these benefits also apply to LWR plutonium recycled into fast reactors. There are benefits for plutonium isotopic separation in fast reactor fuel cycles (particularly removal of Pu-242) but the benefits are less. (author)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

Behavior of Na and K in the extraction process of lithium isotope separation

The extraction behavior of Na and K during lithium isotope separation using benzo-15-crown-5 (B15C5) in chloroform as the extractant was investigated. It was found that potassium was extracted better than sodium and lithium, the metal: B15C5 ratio in the extracted compound was 1: 1 for all metals. It was shown that in the extraction systems with a LiCl concentration higher than 5 mol L{sup -1}, B15C5 was noticeably transferred into aqueous solutions, while concentrated LiCl solutions had a salting-out effect with respect to Na and K.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
DOE OSTI2014

The beam diagnostic instruments in Beijing radioactive ion-beam facilities isotope separator on-line

The beam diagnostic instruments for Beijing Radioactive Ion-beam Facilities Isotope Separator On-Line are introduced [B. Q. Cui, Z. H. Peng, Y. J. Ma, R. G. Ma, B. Tang, T. Zhang, and W. S. Jiang, Nucl. Instrum. Methods 266, 4113 (2008); T. J. Zhang, X. L. Guan, and B. Q. Cui, in Proceedings of APAC 2004, Gyeongju, Korea, 2004, http://www.jacow.org , p. 267]. For low intensity ion beam [30–300 keV/1 pA–10 μA], the beam profile monitor, the emittance measurement unit, and the analyzing slit will be installed. For the primary proton beam [100 MeV/200 μA], the beam profile scanner will be installed. For identification of the nuclide, a beam identification unit will be installed. The details of prototype of the beam diagnostic units and some experiment results will be described in this article.

43 PARTICLE ACCELERATORS↗
DOE OSTI2012

Pulsed CO laser for isotope separation of uranium

This article proposes a technical solution for using a CO laser facility for the industrial separation of uranium used in the production of fuel for nuclear power plants, employing a method of laser isotope separation of uranium with condensation repression in a free jet. The laser operation with nanosecond pulse irradiation can provide an acceptable efficiency in the separating unit and a high efficiency of the laser with the wavelength of 5.3 {mu}m. In the present work we also introduce a calculation model and define the parameters of a mode-locked CO laser with a RF discharge in the supersonic stream. The average pulsed CO laser power of 3 kW is sufficient for efficient industrial isotope separation of uranium in one stage.

07 ISOTOPE AND RADIATION SOURCES↗
DOE OSTI2016

Hydrogen Isotope Separation from Aqueous Streams using Zeolite Membranes

Efficient separation of heavy hydrogen isotopes {sup 3}H (or T, tritium) and {sup 2}H (or D, deuterium) from {sup 1}H has been a long-standing endeavor in nuclear fuel cycle research and development. For example, tritium (half-life 12.3 years) is a fission product from nuclear plants and is found as tritiated water (HTO) in effluent streams from nuclear installations. Tritium must be concentrated and removed from such aqueous streams for waste storage. The separation of deuterium from deuterated water (HDO) has applications in heavy water production, and can also be used as a nonradioactive simulant in HTO separation research. Several methods have been explored such as ion exchange/adsorption and membrane permeation. Adsorption by molecular sieving materials such as zeolites can separate tritiated water from water with moderate selectivity (HTO/H{sub 2}O separation factor∼1.2-1.4) due to a subtle difference in adsorption characteristics between the two species. However, there remains a requirement for high-selectivity continuous separation of heavy hydrogen isotopes from water. Here we demonstrate new results on the use of zeolite membranes as a potential high-performance, low-cost, radiation-stable candidate for such separations. In zeolite membranes, separation of HTO (or HDO) from water would take place by a combination of adsorption and diffusion characteristics. Here we describe the hydrogen isotope separation properties of silicoaluminophosphate (SAPO-34) membranes synthesized on porous α-alumina supports. D{sub 2}O/H{sub 2}O feed mixtures of realistic compositions are used as a non-radioactive simulant for tritiated water feeds. Our results show promising applications of zeolite membranes for hydrogen isotope separation and recovery. In summary, SAPO-34 membranes were fabricated and investigated to demonstrate their pervaporative separation properties for D{sub 2}O-H{sub 2}O binary systems. These membrane exhibit high selectivity (up to ∼19) for D{sub 2}O and good permeance (> 600 GPU) even at low concentrations of D{sub 2}O in the feed, making them highly interesting candidates for capture of heavy hydrogen isotopes (D and T) from aqueous streams encountered in the nuclear fuel cycle. The mechanism of separation appears to involve both diffusivity and adsorption differences as expected in nanoporous materials, even though detailed identification of their respective contributions is a subject of future work. We also hypothesize that tritiated (T{sub 2}O/H{sub 2}O) mixtures will also show similar performance in relation to the present deuterated mixtures. This is planned to be further investigated through pervaporation measurements. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
NASA NTRS1977

Isotope separation using metallic vapor lasers

The isotope U235 is separated from a gasified isotope mixture of U235 and U238 by selectively exciting the former from the ground state utilizing resonant absorption of radiation from precisely tuned lasers. The excited isotope is then selectively ionized by electron bombardment. It then is separated from the remaining isotope mixture by electromagnetic separation.

Russell, G. R.↗
NASA NTRS1976

A status of progress for the Laser Isotope Separation (LIS) process

An overview of the Laser Isotope Separation (LIS) methodology is given together with illustrations showing a simplified version of the LIS technique, an example of the two-photon photoionization category, and a diagram depicting how the energy levels of various isotope influence the LIS process. Applications were proposed for the LIS system which, in addition to enriching uranium, could in themselves develop into programs of tremendous scope and breadth. These include the treatment of radioactive wastes from light-water nuclear reactors, enriching the deuterium isotope to make heavy-water, and enriching the light isotopes of such elements as titanium for aerospace weight-reducing programs. Economic comparisons of the LIS methodology with the current method of gaseous diffusion indicate an overwhelming advantage; the laser process promises to be 1000 times more efficient. The technique could also be utilized in chemical reactions with the tuned laser serving as a universal catalyst to determine the speed and direction of a chemical reaction.

Delionback, L. M.↗
DOE OSTI2024

Chlorine Isotope Separations using Thermal Diffusion

As of the close of 2023 a thermal diffusion isotope separations (TDIS) apparatus was constructed, successful shakedown testing was achieved and enrichments of isotopic concentrations relative to natural abundance 35/37 Cl were collected. Further, the model for these enrichment experiments drove the timing for sampling and other critical, extrapolated functions that are discussed herein. Our decision to move forward in 2024 with the installation of a larger set of separation tubes and associated equipment was based on the successful development of the predictive model. The Chlorine Isotopes Project Team at PNNL is prepared to claim that the installation and hence its separative power is restricted only by the spatial limitations of the laboratory, and this at present appears to be the limiting feature to first pass high enriched 37 Cl.

07 ISOTOPE AND RADIATION SOURCES↗
DOE OSTI2016

Numerical modelling of the flow and isotope separation in centrifuge Iguasu for different lengths of the rotor

Numerical modelling and optimization of the gas flow and isotope separation in the Iguasu gas centrifuge (GC) for uranium enrichment have been performed for different lengths of the rotor. The calculations show that the specific separative power of the GC reduces with the length of the rotor. We show that the reduction of the specific separative power is connected with the growth of the pressure in the optimal regime and corresponding growth of temperature to prevent the working gas sublimation. The specific separative power remains constant with the growth of the rotor length provided that the temperature of the gas is taken to be constant.

07 ISOTOPE AND RADIATION SOURCES↗
DOE OSTI2015

First calibration measurements of an FTIR absorption spectroscopy system for liquid hydrogen isotopologues for the isotope separation system of fusion power plants

Fusion facilities like ITER and DEMO will circulate huge amounts of deuterium and tritium in their fuel cycle with an estimated throughput of kg per hour. One important capability of these fuel cycles is to separate the hydrogen isotopologues (H{sub 2}, D{sub 2}, T{sub 2}, HD, HT, DT). For this purpose the Isotope Separation System (ISS), using cryogenic distillation, as part of the Tritium Enrichment Test Assembly (TRENTA) is under development at Tritium Laboratory Karlsruhe. Fourier transform infrared absorption spectroscopy (FTIR) has been selected to prove its capability for online monitoring of the tritium concentration in the liquid phase at the bottom of the distillation column of the ISS. The actual research-development work is focusing on the calibration of such a system. Two major issues are the identification of appropriate absorption lines and their dependence on the isotopic concentrations and composition. For this purpose the Tritium Absorption IR spectroscopy experiment has been set up as an extension of TRENTA. For calibration a Raman spectroscopy system is used. First measurements, with equilibrated mixtures of H{sub 2}, D{sub 2} and HD demonstrate that FTIR can be used for quantitative analysis of liquid hydro-gen isotopologues and reveal a nonlinear dependence of the integrated absorbance from the D{sub 2} concentration in the second vibrational branch of D{sub 2} FTIR spectra. (authors)

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
DOE OSTI2019

Hydrogen Isotope Separation By a Palladium-Based Membrane

<p style="text-align: justify;">Poster presented at American Institute of Chemical Engineers (AIChE) Annual Conference in Orlando Florida, November 2019Objective: Evaluate the separation of hydrogen isotopes (protium/deuterium) as a function of various process conditions and with various membrane materials in a membrane reactor</p><p style="text-align: justify;"><br></p><p style="text-align: justify;"><br></p>

Means, Nicholas C.↗
DOE OSTI2014

Resonance ionization laser ion sources for on-line isotope separators (invited)

A Resonance Ionization Laser Ion Source (RILIS) is today considered an essential component of the majority of Isotope Separator On Line (ISOL) facilities; there are seven laser ion sources currently operational at ISOL facilities worldwide and several more are under development. The ionization mechanism is a highly element selective multi-step resonance photo-absorption process that requires a specifically tailored laser configuration for each chemical element. For some isotopes, isomer selective ionization may even be achieved by exploiting the differences in hyperfine structures of an atomic transition for different nuclear spin states. For many radioactive ion beam experiments, laser resonance ionization is the only means of achieving an acceptable level of beam purity without compromising isotope yield. Furthermore, by performing element selection at the location of the ion source, the propagation of unwanted radioactivity downstream of the target assembly is reduced. Whilst advances in laser technology have improved the performance and reliability of laser ion sources and broadened the range of suitable commercially available laser systems, many recent developments have focused rather on the laser/atom interaction region in the quest for increased selectivity and/or improved spectral resolution. Much of the progress in this area has been achieved by decoupling the laser ionization from competing ionization processes through the use of a laser/atom interaction region that is physically separated from the target chamber. A new application of gas catcher laser ion source technology promises to expand the capabilities of projectile fragmentation facilities through the conversion of otherwise discarded reaction fragments into high-purity low-energy ion beams. A summary of recent RILIS developments and the current status of laser ion sources worldwide is presented.

43 PARTICLE ACCELERATORS↗
DOE OSTI2023

Commissioning of the Advanced Rare Isotope Separator ARIS at FRIB

The Facility for Rare Isotope Beams (FRIB) at Michigan State University (MSU) consists of a newly constructed linear accelerator and fragment separator that are designed for enhanced production rates of rare isotopes for use in research and other societal applications. Recent activities through to August 2022 took place to commission the Advanced Rare Isotope Separator (ARIS) and carry out the first experiments. This followed commissioning of the newly constructed linac that is designed to provide orders of magnitude higher beam power than the previously coupled cyclotrons. This required that more advanced target, beam dump, and collimation systems of the new separator be designed and constructed to sustain unprecedented conditions by heavy ion beams. Commissioning with ~1 kW beams began recently and results from activities that began in late 2021 are reported here. Comparisons between the previous and current facilities are provided.

43 PARTICLE ACCELERATORS↗
DOE OSTI2023

Comparison of Designs of Hydrogen Isotope Separation Columns by Numerical Modeling

Mixtures of gas-phase hydrogen isotopologues (diatomic combinations of protium, deuterium, and tritium) can be separated using columns containing a solid such as palladium that reversibly absorbs hydrogen. A temperature-swing process can transport hydrogen into or out of a column by inducing temperature-dependent absorption or desorption reactions. Here, we consider two designs: a thermal cycling absorption process, which moves hydrogen back and forth between two columns, and a simulated moving bed (SMB), where columns are in a circular arrangement. We present a numerical mass and heat transport model of absorption columns for hydrogen isotope separation. It includes a detailed treatment of the absorption–desorption reaction for palladium. By comparing the isotope concentrations within the columns as a function of position and time, we observe that SMB can lead to sharper separations for a given number of thermal cycles by avoiding the remixing of isotopes.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗