• Title/Summary/Keyword: Isotope separation system

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Research Trend of Crystalline Porous Materials for Hydrogen Isotope Separation via Kinetic Quantum Sieving (운동 양자 체(Kinetic Quantum Sieving) 효과를 가진 나노다공성 물질을 활용한 수소동위원소 분리 동향)

  • Lee, Seulji;Oh, Hyunchul
    • Korean Journal of Materials Research
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    • v.31 no.8
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    • pp.465-470
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    • 2021
  • Deuterium is a crucial clean energy source required for nuclear fusion and is a future resource needed in various industries and scientific fields. However, it is not easy to enrich deuterium because the proportion of deuterium in the hydrogen mixture is scarce, at approximately 0.016 %. Furthermore, the physical and chemical properties of the hydrogen mixture and deuterium are very similar. Therefore, the efficient separation of deuterium from hydrogen mixtures is often a significant challenge when using modern separation technologies. Recently, to effectively separate deuterium, studies utilizing the 'Kinetic Quantum Sieving Effect (KQS)' of porous materials are increasing. Therefore, in this review, two different strategies have been discussed for improving KQS efficiency for hydrogen isotope separation performance using nanoporous materials. One is the gating effect, which precisely controls the aperture locally by adjusting the temperature and pressure. The second is the breathing phenomenon, utilizing the volume change of the structure from closed system to open system. It has been reported that efficient hydrogen isotope separation is possible using these two methods, and each of these effects is described in detail in this review. In addition, a specific-isotope responsive system (e.g., 2nd breathing effect in MIL-53) has recently been discovered and is described here as well.

Hydrogen Isotope Separation by using Zeolitic lmidazolate Frameworks (ZIF-11) (ZIF-11을 이용한 수소 동위원소 분리)

  • Lee, Seulji;Oh, Hyunchul
    • Korean Journal of Materials Research
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    • v.30 no.12
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    • pp.655-659
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    • 2020
  • Hydrogen isotopes (i.e. deuterium and tritium) are supplied to the tokamak in the International Thermonuclear Experimental Reactor (ITER) fuel cycle. One important part of the ITER fuel cycle is the recycling of unused fuel back to the tokamak, as almost 99 % of fuel is unburned during fusion reaction. For this, cryogenic distillation has been used in the isotope separation system (ISS) of ITER, but this technique tends to be energy-intensive and to have low selectivity (typically below 1.5 at 24 K). Recently, efficient isotope separation by porous materials has been reported in the so-called quantum sieving process. Hence, in this study, hydrogen isotope adsorption behavior is studied using chemically stable ZIF-11. At low temperature (40 K ~ 70 K), the adsorption increases and the sorption hysteresis becomes stronger as the temperature increases to 70K. Molar ratio of deuterium to hydrogen based on the isotherms shows the highest (max. 14) ratio at 50 K, confirming the possibility of use as a potential isotope separation material.

Development of EPICS-IOC Measuring Magnetic Field at A/Q separator for Separating Specific Ions (가속이온 분리를 위한 A/Q Separator에서 자장측정용 EPICS-IOC 개발)

  • Lee, Su-Yeong;Yim, Hee-Joong;Kim, Jae-Hong;Mun, Jun-Yeong;Park, Mi-Jeong;Lee, Sang-Il;Lee, Dong-Hoon
    • Journal of the Institute of Convergence Signal Processing
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    • v.22 no.3
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    • pp.91-98
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    • 2021
  • The installation and performance test of the ISOL (Isotope Separation On Line) system for the generation and separation of Rare Isotopes (RI) beams is in progress at the Rare Isotope Science Project (RISP), Institute for Basic Science (IBS). The various RI beams generated by the ISOL target/ion source go through the beam lines and separators, and only the RI beam desired by the user is selected and transmitted to the superconducting linear accelerator at the downstream of the ISOL. In the ISOL system, two separators are installed to separate a specific RI beam, and control is performed by the Experimental Physics and Industrial Control System (EPICS). In this study, an EPICS IOC (Input-Output Control) was developed to measure the magnetic field of a dipole magnet for mass separation of a multivalent (n+) RI beam in the A/Q separator, which is one of the ISOL RI beam separators. The operational stability of the A/Q separator was tested through a magnetic field measurement using a Hall probe.

Studies on Setting up of Radioimmunoassay System of Thyroid Stimulating Hormone (갑상선자극(甲狀腺刺戟)호르몬의 방사면역측정법(放射免疫測定法) 확립(確立)에 관한 연구(硏究))

  • Kim, Jae-Rok;Park, Kyung-Bae;Awh, Ok-Doo
    • The Korean Journal of Nuclear Medicine
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    • v.20 no.1
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    • pp.75-83
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    • 1986
  • Various TSH RIA kit components were prepared. Conditions for $^{125}I$ labelling of h-TSH were optimized by diminishing the amount of chloramine-T, ertending reaction time and lowering reaction temperature. Yield, specific activity, and immunological activity could be maintained moderately under such mild reaction conditions. The mixture of polyethyleneglycol(PEG) and second antibody worked effectively as a B/F separation agent. Even though the mixture was made with more diluted PEG and second antibody than those of using the sole component separately, the tine required for the B/F separation was shorter in case of using the mixture. The sequential saturation technique was efficient than those of applying ordinary equilibrium saturation technique in assay sensitivity and assay precision points of view.

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Separation of Lithium Isotopes by Porous Sulfonated Styrene-Divinylbenzene Copolymer Ionexchanger (Porous Sulfonated Styrene-Divinylbenzene Copolymer Ionexchanger 에 의한 리튬 동위원소의 분리)

  • Dong Won Kim;Ki Suck Maeng;Hae Young Song;Hae Il Ryu
    • Journal of the Korean Chemical Society
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    • v.27 no.3
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    • pp.189-193
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    • 1983
  • The lithium isotopes separation experiments were carried out in hydrochloric acid with cation exchanger systerns. In these experiments were employed porous sulfonated styrene-divinylbenzene copolymer and Dowex 50w-x8 as cation exchanger. The contents of lithium of the fraction were determined with atomic absorption spectrophotometer. The relative mass of lithium isotopes of the fractions was analyzed on a mass spectrometer. The isotope separation factors of lithium were calculated from the isotope compositions of these eluted fractions. Separation factor for the system in hydrochloric acid and porous sulfonated styrene-divinylbenzene copolymer was found to be 1.0020, and for the case of system in hydrochloric acid and Dowex 50w-x8 was 1.0011${\om}$0.0002. From these results, we found that the separation factor for porous sulfonated styrene-divinylbenzene copolymer ionexchanger is larger than value of Dowex 50w-x8 ionexchanger.

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Storage and Delivery of Hydrogen Isotopes (삼중수소 저장기술)

  • Chung, Hong-Suk;Chung, Dong-You;Koo, Dae-Seo;Lee, Ji-Sung;Shim, Myung-Hwa;Cho, Seung-Yon;Jung, Ki-Jung;Yun, Sei-Hun
    • Journal of Hydrogen and New Energy
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    • v.22 no.3
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    • pp.372-379
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    • 2011
  • A nuclear fusion fuel cycle plant is composed of various subsystems such as a hydrogen isotope storage and delivery system, a tokamak exhaust processing system, and a hydrogen isotope separation system. Korea shares in the construction of its ITER fuel cycle plant with the EU, Japan, and the US, and is responsible for the development and supply of the storage and delivery system. The authors thus present details on the development status of hydrogen isotope storage technologies for nuclear fusion fuel cycle plants. We have developed various hydride beds of different size. We have realized a hydrogen delivery rate of 12.5 $Pam^3/s$ with a typical 1242g-ZrCo bed.

Tritium Fuel Cycle Technology of ITER Project (ITER 사업의 삼중수소 연료주기 기술)

  • Yun, Sei-Hun;Chang, Min-Ho;Kang, Hyun-Goo;Kim, Chang-Shuk;Cho, Seung-Yon;Jung, Ki-Jung;Chung, Hong-Suk;Song, Kyu-Min
    • Journal of Hydrogen and New Energy
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    • v.23 no.1
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    • pp.56-64
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    • 2012
  • The ITER fuel cycle is designed for DT operation in equimolar ratio. It involves not only a group of fuelling system and torus cryo-pumping system of the exhaust gases through the divertor from the torus in tokamak plant, but also from the exhaust gas processing of the fusion effluent gas mixture connected to the hydrogen isotope separation in cryogenic distillation to the final safe storage & delivery of the hydrogen isotopes in tritium plant. Tritium plant system supplies deuterium and tritium from external sources and treats all tritiated fluids in ITER operation. Every operation and affairs is focused on the tritium inventory accountancy and the confinement. This paper describes the major fuel cycle processes and interfaces in the tritium plant in aspects of upcoming technologies for future hydrogen and/or hydrogen isotope utilization.

Rapid Cooling Performance Evaluation of a ZrCo bed for a Hydrogen Isotope Storage (수소동위원소 저장용 ZrCo용기의 급속 냉각 성능 평가)

  • Lee, Jungmin;Park, Jongchul;Koo, Daeseo;Chung, Dongyou;Yun, Sei-Hun;paek, Seungwoo;Chung, Hongsuk
    • Journal of Hydrogen and New Energy
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    • v.24 no.2
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    • pp.128-135
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    • 2013
  • The nuclear fuel cycle plant is composed of various subsystems such as a fuel storage and delivery system (SDS), a tokamak exhaust processing system, a hydrogen isotope separation system, and a tritium plant analytical system. Korea is sharing in the construction of the International Thermonuclear Experimental Reactor (ITER) fuel cycle plant with the EU, Japan, and the US, and is responsible for the development and supply of the SDS. Hydrogen isotopes are the main fuel for nuclear fusion reactors. Metal hydrides offer a safe and convenient method for hydrogen isotope storage. The storage of hydrogen isotopes is carried out by absorption and desorption in a metal hydride bed. These reactions require heat removal and supply respectively. Accordingly, the rapid storage and delivery of hydrogen isotopes are enabled by a rapid cooling and heating of the metal hydride bed. In this study, we designed and manufactured a vertical-type hydrogen isotope storage bed, which is used to enhance the cooling performance. We present the experimental details of the cooling performances of the bed using various cooling parameters. We also present the modeling results to estimate the heat transport phenomena. We compared the cooling performance of the bed by testing different cooling modes, such as an isolation mode, a natural convection mode, and an outer jacket helium circulation mode. We found that helium circulation mode is the most effective which was confirmed in our model calculations. Thus we can expect a more efficient bed design by employing a forced helium circulation method for new beds.

Ln-resin and HIBA Method for La-Ce and Sm-Nd Isotope Measurement (La-Ce 및 Sm-Nd 동위원소계 측정을 위한 란탄-레진법과 HIBA(Hydroxy Isobutyric Acid)분리법의 상호비교)

  • Lee, Seung-Gu;Lee, Hyomin;Asahara, Yoshihiro;Lee, Mi-Jeong;Choo, MiKyeong;Lee, SeungRyeol
    • The Journal of the Petrological Society of Korea
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    • v.21 no.4
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    • pp.431-439
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    • 2012
  • A column chemistry is the most useful tools for isolating the elements of interest in isotope geochemistry. Here we introduce the chemical experimental procedure for Sm, Nd, La and Ce separation such as Teflon powder or Ln-resin method using HDEHP of KIGAM, KBSI, KOPRI and ${\alpha}$-HIBA(${\alpha}$-Hydroxy Isobutyric acid) method of Nagoya University, Japan. This technical report will provide an useful information in selecting the experiment method for rare earth element isotope system study such as Sm-Nd and La-Ce isotope system.

Enrichment of Lithium Isotopes by Cation Exchange Chromatography (양이온 교환 크로마토그래피에 의한 리튬 동위원소의 농축)

  • Kim, Dong Won;Kim, Chang Suck;Choi, Ki Young;Jeon, Young Shin;Jeong, Young Kyu;Park, Sung Up
    • Analytical Science and Technology
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    • v.7 no.2
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    • pp.201-204
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    • 1994
  • Cation exchange column chromatography of lithium was carried out to investigate the lithium isotope separation in aqueous ion exchange system. A Pyrex glass column of $50cm{\times}6mm$ inner radius with a water jacket was used as the separation column in experiment. Upon column chromatography using hydrochloric and succinic acid mixtures as an elunent, single separation factor, ${\alpha}$, 1.0068 was obtained. From the experiment, it was found that $^6Li$ was enriched in the resin phase and $^7Li$ in the solution phase.

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