• Title/Summary/Keyword: Nuclear Reaction

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A Study on the Hydriding Reaction of Pre-oxidized Zr Alloys (산화막을 입힌 지르코늄 합금의 수소화 반응에 관한 연구)

  • Kim, Sun-Ki;Bang, Je-Geon;Kim, Dae-Ho;Lim, Ik-Sung;Yang, Yong-Sik;Song, Kun-Woo
    • Journal of the Korean Ceramic Society
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    • v.47 no.2
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    • pp.106-112
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    • 2010
  • This paper presents some experimental results on incubation time for massive hydriding of Zr alloys with oxide thickness. Oxide effects experiments on massive hydriding reaction of commercial Zr alloy claddings and pre-oxidized Zr alloys with hydrogen gas were carried out in the temperature range from 300 to $400^{\circ}C$ with thermo-gravimetric apparatus. Experimental results for oxide effects on massive hydriding kinetics show that incubation time is not proportional to oxide thickness and that the massive hydriding kinetics of pre-filmed Zr alloys follows linear kinetic law and the hydriding rate are similar to that of oxide-free Zr alloys once massive hydriding is initiated. There was a difference in micro-structures between oxide during incubation time and oxide after incubation time. Physical defects such as micro-cracks and pores were observed in only oxide after incubation time. Therefore, the massive hydriding of Zr alloys seems to be ascribed to short circuit path, mechacical or physical defects, such as micro-cracks and pores in the oxide rather than hydrogen diffusion through the oxide resulting from the increase of oxygen vacancies in the hypostoichiometric oxide.

Measurement of Neutron Production Double-differential Cross-sections on Carbon Bombarded with 430 MeV/Nucleon Carbon Ions

  • Itashiki, Yutaro;Imahayashi, Youichi;Shigyo, Nobuhiro;Uozumi, Yusuke;Satoh, Daiki;Kajimoto, Tsuyoshi;Sanami, Toshiya;Koba, Yusuke;Matsufuji, Naruhiro
    • Journal of Radiation Protection and Research
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    • v.41 no.4
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    • pp.344-349
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    • 2016
  • Background: Carbon ion therapy has achieved satisfactory results. However, patients have a risk to get a secondary cancer. In order to estimate the risk, it is essential to understand particle transportation and nuclear reactions in the patient's body. The particle transport Monte Carlo simulation code is a useful tool to understand them. Since the code validation for heavy ion incident reactions is not enough, the experimental data of the elementary reaction processes are needed. Materials and Methods: We measured neutron production double-differential cross-sections (DDXs) on a carbon bombarded with 430 MeV/nucleon carbon beam at PH2 beam line of HIMAC facility in NIRS. Neutrons produced in the target were measured with NE213 liquid organic scintillators located at six angles of 15, 30, 45, 60, 75, and $90^{\circ}$. Results and Discussion: Neutron production double-differential cross-sections for carbon bombarded with 430 MeV/nucleon carbon ions were measured by the time-of-flight method with NE213 liquid organic scintillators at six angles of 15, 30, 45, 60, 75, and $90^{\circ}$. The cross sections were obtained from 1 MeV to several hundred MeV. The experimental data were compared with calculated results obtained by Monte Carlo simulation codes PHITS, Geant4, and FLUKA. Conclusion: PHITS was able to reproduce neutron production for elementary processes of carbon-carbon reaction precisely the best of three codes.

Dissolution behavior of SrO into molten LiCl for heat reduction in used nuclear fuel

  • Kang, Dokyu;Amphlett, James T.M.;Choi, Eun-Young;Bae, Sang-Eun;Choi, Sungyeol
    • Nuclear Engineering and Technology
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    • v.53 no.5
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    • pp.1534-1539
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    • 2021
  • This study reports on the dissolution behavior of SrO in LiCl at varying SrO concentrations from low concentrations to excess. The amount of SrO dissolved in the molten salt and the species present upon cooling were determined. The thermal behavior of LiCl containing various concentrations of SrO was investigated. The experimental results were compared with results from the simulated results using the HSC Chemistry software package. Although the reaction of SrO with LiCl in the standard state at 650 ℃ has a slightly positive Gibbs free energy, SrO was found to be highly soluble in LiCl. Experimentally determined SrO concentrations were found to be considerably higher than those present in used nuclear fuel (<2 g/kg). As Sr-90 is one of the most important heat-generating nuclides in used nuclear fuel, this finding will be impactful in the development of fast, simple, and proliferation-resistant heat reduction processes for used nuclear fuel without the need for separating nuclear materials. Heat reduction is important as it decreases both the volume necessary for final disposal and the worker handling risk.

Experimental Study for the Identification of the Nascent Product of OH Heterogeneous Reaction with NaCl using Chemical Ionization Mass Spectrometry

  • Park, Jong-Ho;Ivanov, Andrey V.;Molina, Mario J.
    • Mass Spectrometry Letters
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    • v.3 no.4
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    • pp.108-111
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    • 2012
  • An experimental study on the nascent product of the OH heterogeneous reaction with NaCl was performed under dry and wet conditions using a bead-filled flow tube system coupled to a high-pressure chemical ionization mass spectrometer. The ozone concentration in the flow tube for the atomic hydrogen removal was varied in order to control the conversion reaction of molecular chlorine into HCl for the identification of the nascent product. The mass spectrometric observation was that the $O_3$ introduction reduced the concentration HCl, while it increased the concentration of $Cl_2$ and ClO. Based on the experimental results, we suggest that the nascent product of the titled reaction is gaseous $Cl_2$, which is followed by fast conversion into HCl in presence of H. No significant difference in the concentration profile between under dry and wet (RH = 2%) conditions was observed.

Preparation and Animal Imaging of $^{153}Sm$-EDTMP as a Bone Seeking Radiopharmaceutical (골친화성 방사성의약품 $^{153}Sm$-EDTMP의 합성과 동물영상)

  • Choi, Tae-Hyun;Kim, Se-Jung;Shin, Byung-Chul;Woo, Kwang-Sun;Chung, Wee-Sup;Choi, Chang-Woon;Lim, Sang-Moo
    • The Korean Journal of Nuclear Medicine
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    • v.39 no.1
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    • pp.44-48
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    • 2005
  • Purpose: Ethylenediamine-tetramethylenephosphonic acid (EDTMP) has widely used chelator for the labeling of bone seeking radiopharmaceuticals complexed with radiometals. $^{153}Sm$ can be produced by the HANARO reactor at the Korea Atomic Energy Research Institute, Taejon, Korea. $^{153}Sm$ has favourable radiation characteristics $T1/2=46.7\;h,\;{\beta}_{max}=0.81\;MeV\;(20%),\;0.71\;MeV\;(49%),\;0.64\;MeV\;(30%)\;and\;{\gamma}=103\;keV\;(30%)$ emission which is suitable for imaging purposes during therapy. We investigated the labeling condition of $^{153}Sm$-EDTMP and imaging of $^{153}Sm$-EDTMP in normal rats. Materials and methods: EDTMP 20 mg was solved in 0.1 mL 2 M NaOH. $^{153}SmCl^3$ was added to EDTMP solution and pH of the reaction mixtures was adjusted to 3 and 12, respectively. Radiochemical purity was determined with paper chromatography. After 30 min. reaction, reaction mixtures were neutralized to pH 7.4, and the stability was estimated upto 120 hrs. Imaging studies of each reaction were perfomed in normal rats (37 MBq/0.1 mL). Results: The labeling yield of $^{153}Sm$-EDTMP was 99%. The stability of pH 8 reaction at 60, 96 and 120 hr was 99%, 95%, 89% and that of pH 12 at 36, 60, 96 and 120 hr was 99%, 95%, 88%, 66%, respectively. The $^{153}Sm$-EDTMP showed constantly higher bone uptake from 2 to 48 hr after injection. Conclusion: $^{153}Sm$-EDTMP, labeled at pH 8 reaction condition, has been stably maintained. Image of $^{153}Sm$-EDTMP at 2, 24, 48 hr after injection, demonstrate that $^{153}Sm$-EDTMP is a good bone seeking radiopharmaceuticals.

Application of ecological interface design in nuclear power plant (NPP) operator support system

  • Anokhin, Alexey;Ivkin, Alexey;Dorokhovich, Sergey
    • Nuclear Engineering and Technology
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    • v.50 no.4
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    • pp.619-626
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    • 2018
  • Most publications confirm that an ecological interface is a very efficient tool to supporting operators in recognition of complex and unusual situations and in decision-making. The present article describes the experience of implementation of an ecological interface concept for visualization of material balance in a drum separator of RBMK-type NPPs. Functional analysis of the domain area was carried out and revealed main factors and contributors to the balance. The proposed ecological display was designed to facilitate execution of the most complicated cognitive operations, such as comparison, summarizing, prediction, etc. The experimental series carried out at NPPs demonstrated considerable reduction of operators' mental load, time of reaction, and error rate.

How the New York Times Portrayed the 2010 Brazil-Turkey-Iran Nuclear Deal: A Critical Discourse Analysis

  • Esfandiary, Esmaeil
    • Journal of Contemporary Eastern Asia
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    • v.14 no.2
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    • pp.57-68
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    • 2015
  • This paper examines the New York Times' reaction to the 2010 Brazil-Turkey-Iran (BTI) nuclear deal, the very last diplomatic effort before the imposition of international sanctions track over the following years. The New York Times' (NYT) coverage of the deal is examined using the Critical Discourse Analytic (CDA) approach formulated by Teun van Dijk. The results show a strong bias against the BTI deal throughout the NYT's news coverage. The overarching theme in cover-age of the deal is the imputation of malignant intentions on the part of both Iran ("to kill time to further its nuclear weapons program") and Brazil and Turkey ("to advance their own business dealings with Iran and gaining international recognition"). Also, non-relevant information is used to imply a threat of Iranian development of nuclear weapons. Moreover, the NYT leaves almost totally "unsaid" that president Obama had asked Brazilian and Turkish leaders to go to Tehran and get this deal. Therefore, the NYT basically echoed, and legitimized, discursive practices of the U.S. government on the deal.

Validation of the Excore Detector Module of PANBOX 2

  • Kim, Du-Ill;Kang, Jung-Kil;Hwang, Sun-Tack;Kim, Yeong-Il;H. Finnemann;R. Boer
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.130-136
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    • 1998
  • In the PANBOX 2 system an excore detector module simulating the excore signal responses during a short term transient is implemented in order to simulate the reaction of the flux detector and control system upon rapid power changes as it occurs e. g, in rod drop events. This module has been verified in the past by comparison calculations with the PANBOX 1 system. This report describes additional PANBOX 2 validation calculations which have bee compared with experiment data measured at german plant KKG, cycle 1, for a rod drop event. In general, the PANBOX 2 results are in very good agreement with the KKG experiments. Therefore it is concluded that the excore detector model of PANBOX 2 is successfully validated.

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Removal of Uranium from Aqueous Solution by Alginate Beads

  • Yu, Jing;Wang, Jianlong;Jiang, Yizhou
    • Nuclear Engineering and Technology
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    • v.49 no.3
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    • pp.534-540
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    • 2017
  • The adsorption of uranium (VI) by calcium alginate beads was examined by batch experiments. The effects of environmental conditions on U (VI) adsorption were studied, including contact time, pH, initial concentration of U (VI), and temperature. The alginate beads were characterized by using scanning electron microscopy, transmission electron microscopy, X-ray photoelectron spectroscopy, and Fourier transform infrared spectroscopy. Fourier transform infrared spectra indicated that hydroxyl and alkoxy groups are present at the surface of the beads. The experimental results showed that the adsorption of U (VI) by alginate beads was strongly dependent on pH, the adsorption increased at pH 3~7, then decreased at pH 7~9. The adsorption reached equilibrium within 2 minutes. The adsorption kinetics of U (VI) onto alginate beads can be described by a pseudo first-order kinetic model. The adsorption isotherm can be described by the Redlich-Peterson model, and the maximum adsorption capacity was 237.15 mg/g. The sorption process is spontaneous and has an exothermic reaction.

Modeling and experimental production yield of 64Cu with natCu and natCu-NPs in Tehran Research Reactor

  • Karimi, Zahra;Sadeghi, Mahdi;Ezati, Arsalan
    • Nuclear Engineering and Technology
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    • v.51 no.1
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    • pp.269-274
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    • 2019
  • $^{64}Cu$ is a favorable radionuclide in nuclear medicine applications because of its unique characteristics such as three types of decay (electron capture, ${\beta}^-$ and ${\beta}^+$) and 12.7 h half-life. Production of $^{64}Cu$ by irradiation $^{nat}Cu$ and $^{nat}CuNPs$ in Tehran Research Reactor was investigated. The characteristics of copper nanoparticles were investigated with SEM, TEM and XRD analysis. The cross section of $^{63}Cu(n,{\gamma})^{64}Cu$ reaction was done with TALYS-1.8 code. The activity value of $^{64}Cu$ was calculated with theoretical approach and MCNPX-2.6 code. The results were compared with related experimental results which showed good adaptations between them.