• Title/Summary/Keyword: Helium impurities

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Analysis of Trace Impurities in The Bulk Gases by a Cold Concentration Method (저온 농축법에 의한 극미량 성분 가스분석)

  • Lee Taeck-Hong;Hong So Young;Jung Woo Chan;Kim Young Rak;Suh Jung Woo;Han Ju Tack;Park Doo Seon;Son Moo Ryong
    • 한국가스학회:학술대회논문집
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    • 1997.09a
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    • pp.260-265
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    • 1997
  • Analysis of trace impurities in the bulk .gas has been very important with the development of semi-conductor related industry. In the paper, we reported the analysis of the trace impurites of carbon monoxide and methane in the bulk helium and hydrogen by the GC-TCD with a cold nitrogen trap. We compared these results by the paraallel analysis. All data showed a good correspondence, showing reliable statistical error ranges.

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Effects of alloying elements on the mechanical and high temperature corrosion properties of solid-solution hardening nickel-base alloy (Ni-Cr계 고용강화형 합금에서 조성에 따른 기계적 및 고온부식 특성 평가)

  • Jung, Sujin;Kim, Dong-Jin
    • Corrosion Science and Technology
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    • v.13 no.5
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    • pp.178-185
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    • 2014
  • Alloy 617 is considered as a candidate Ni-based superalloy for the intermediate heat exchanger (IHX) of a very high-temperature gas reactor (VHTR) because of its good creep strength and corrosion resistance at high temperatures. Helium is used as a coolant in a VHTR owing to its high thermal conductivity, inertness, and low neutron absorption. However, helium inevitably includes impurities that create an imbalance in the surface reactivity at the interface of the coolant and the exposed materials. As the Alloy 617 has been exposed to high temperatures at $950^{\circ}C$ in the impure helium environment of a VHTR, the degradation of material is accelerated and mechanical properties decreased. The high-temperature strength, creep, and corrosion properties of the structural material for an IHX are highly important to maintain the integrity in a harsh environment for a 60 year period. Therefore, an alloy superior to alloy 617 should be developed. In this study, the mechanical and high-temperature corrosion properties for Ni-Cr alloys fabricated in the laboratory were evaluated as a function of the grain boundary strengthening and alloying elements. The ductility increased and decreased by increasing the amount of Mo and Cr, respectively. Surface oxide was detached during the corrosion test, when Al was not added to alloy. However the alloy with Al showed improved oxide adhesive property without significant degradation and mechanical property. Aluminum seems to act as an anti-corrosive role in the Ni-based alloy.

Monte Carlo Calculation for Production Cross-Sections of Projectile's Isotopes from Therapeutic Carbon and Helium Ion Beams in Different Materials

  • Quazi Muhammad Rashed Nizam;Asif Ahmed;Iftekhar Ahmed
    • Journal of Radiation Protection and Research
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    • v.48 no.4
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    • pp.204-212
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    • 2023
  • Background: Isotopes of the projectile may be produced along the beam path during the irradiation of a target by a heavy ion due to inelastic interactions with the media. This study analyzed the production cross-section of carbon (C) and Helium (He) projectile's isotopes resulting from the interactions of these beams with different materials along the beam path. Materials and Methods: In this study, we transport C and He ion beams through different materials. This transportation was made by the Monte Carlo simulation. Particle and Heavy Ion Transport code System (PHITS) has been used for this calculation. Results and Discussion: It has been found that 10C, 11C, and 13C from the 12C ion beam and 3He from the 4He ion beam are significant projectile's isotopes that have higher flux than other isotopes of these projectiles. The 4He ion beam has a higher projectile's isotope production cross-section along the beam path, which adds more impurities to the beam than the 12C ion beam. These projectile's isotopes from both the 12C and 4He ion beams have higher production cross-sections in hydrogenous materials like water or polyethylene. Conclusion: It is important to distinguish these projectile's isotopes from the primary beam particles to obtain a precise and accurate cross-section result by minimizing the error during measurement with a nuclear track detector. This study will show the trend of the production probability of projectile's isotopes for these ion beams.

Characterization of a-C/B:H thin films for KSTAR boronization

  • Sun, Jong-Ho;Hong, Suk-Ho;Woo, Hyun-Jong;Park, Eun-Kyong;Kim, Hye-Ran;Chung, Kyu-Sun
    • Proceedings of the Korean Vacuum Society Conference
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    • 2010.02a
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    • pp.414-414
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    • 2010
  • KSTAR vacuum vessel has been boronized by carborane ($C_2B_{10}H_{12}$) to reduce various kinds of impurities including carbon and oxygen from the wall, since carborane is solid, non-toxic, non-explosive and is easily evaporated, while diborane ($B_2D_6$) is toxic and explosive. To find the best wall condition for the removal of contaminants before application to KSTAR, various amounts (0.3g, 0.5g, 1g) of carborane are tested in a test chamber, where filament discharge was generated in the mixture of helium and carborane with the same KSTAR target pressure (~ 5 mTorr) from base pressure (${\sim}10^-7\;Torr$). Discharge is performed by a pulse sequence mode with 3 second power on and 5 second power off. Deposited films of a-C/B:H are characterized by ellipsometery, AES and XPS, and are compared with those of KSTAR.

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Prediction of the Tritium Behavior in Very High Temperature Gas Cooled Reactor Using TRITGO (TRITGO 코드를 이용한 초고온가스로 (VHTR) 삼중 수소 거동 예측)

  • Park, Jong-Hwa;Park, Ik-Kyu;Lee, Won-Jae
    • Journal of Radiation Protection and Research
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    • v.33 no.3
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    • pp.113-120
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    • 2008
  • In this study, The TRITGO code was introduced, which can predict the amount of tritium production, it's transport, removal, distribution and the level of contamination for the produced hydrogen by the tritium on the VHTR (very high temperature gas cooled reactor). The TRITGO code was improved so that the permeation to the IS Iodine Sulfide) loop for producing the hydrogen can be simulated. The contamination level of the produced hydrogen by the tritium was predicted by the improved code for the VHTR with 600MW thermal power. The contamination level for the produced hydrogen by tritium was predicted as 0.055 Bq/$H_2-g$. This level is three order of lower than the regulation value of 56 Bq/$H_2-g$ from Japan. From this study, the following results were obtained. it is important that the fuel coating (SiC layer) should be kept intact to prevent the tritium from releasing. Also it is necessary that the level of impurity such as 3He and Li in the helium coolant and the reflector consisting of the graphite should be kept as low as possible. It was found that the capacity of the purification system for filtering the impurities directly from the coolant will be the important design parameter.

Facile [11C]PIB Synthesis Using an On-cartridge Methylation and Purification Showed Higher Specific Activity than Conventional Method Using Loop and High Performance Liquid Chromatography Purification (Loop와 HPLC Purification 방법보다 더 높은 비방사능을 보여주는 카트리지 Methylation과 Purification을 이용한 손쉬운 [ 11C]PIB 합성)

  • Lee, Yong-Seok;Cho, Yong-Hyun;Lee, Hong-Jae;Lee, Yun-Sang;Jeong, Jae Min
    • The Korean Journal of Nuclear Medicine Technology
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    • v.22 no.2
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    • pp.67-73
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    • 2018
  • $[^{11}C]PIB$ synthesis has been performed by a loop-methylation and HPLC purification in our lab. However, this method is time-consuming and requires complicated systems. Thus, we developed an on-cartridge method which simplified the synthetic procedure and reduced time greatly by removing HPLC purification step. We compared 6 different cartridges and evaluated the $[^{11}C]PIB$ production yields and specific activities. $[^{11}C]MeOTf$ was synthesized by using TRACERlab FXC Pro and was transferred into the cartridge by blowing with helium gas for 3 min. To remove byproducts and impurities, cartridges were washed out by 20 mL of 30% EtOH in 0.5 M $NaH_2PO_4$ solution (pH 5.1) and 10 mL of distilled water. And then, $[^{11}C]PIB$ was eluted by 5 mL of 30% EtOH in 0.5 M $NaH_2PO_4$ into the collecting vial containing 10 mL saline. Among the 6 cartridges, only tC18 environmental cartridge could remove impurities and byproducts from $[^{11}C]PIB$ completely and showed higher specific activity than traditional HPLC purification method. This method took only 8 ~ 9 min from methylation to formulation. For the tC18 environmental cartridge and conventional HPLC loop methods, the radiochemical yields were $12.3{\pm}2.2%$ and $13.9{\pm}4.4%$, respectively, and the molar activities were $420.6{\pm}20.4GBq/{\mu}mol$ (n=3) and $78.7{\pm}39.7GBq/{\mu}mol$ (n=41), respectively. We successfully developed a facile on-cartridge methylation method for $[^{11}C]PIB$ synthesis which enabled the procedure more simple and rapid, and showed higher molar radio-activity than HPLC purification method.