• Title/Summary/Keyword: Fission

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SELECTIVE REDUCTION OF ACTIVE METAL CHLORIDES FROM MOLTEN LiCl-KCl USING LITHIUM DRAWDOWN

  • Simpson, Michael F.;Yoo, Tae-Sic;Labrier, Daniel;Lineberry, Michael;Shaltry, Michael;Phongikaroon, Supathorn
    • Nuclear Engineering and Technology
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    • v.44 no.7
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    • pp.767-772
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    • 2012
  • In support of optimizing electrorefining technology for treating spent nuclear fuel, lithium drawdown has been investigated for separating actinides from molten salt electrolyte. Drawdown reaction selectivity is a major issue that requires investigation, since the goal is to remove actinides while leaving the fission products and other components in the salt. A series of lithium drawdown tests with surrogate fission product chlorides was run to obtain selectivity data with non-radioactive salts, develop a predictive model, and draw conclusions about the viability of using this process with actinide-loaded salt. Results of tests with CsCl, $LaCl_3$, $CeCl_3$, and $NdCl_3$ are reported here. Equilibrium was typically achieved in less than 10 hours of contact between lithium metal and molten salt under well-stirred conditions. Maintaining low oxygen and water impurity concentrations (<10 ppm) in the atmosphere was observed to be critical to minimize side reactions and maintain stable salt compositions. An equilibrium model has been formulated and fit to the experimental data. Good fits to the data were achieved. Based on analysis and results obtained to date, it is concluded that clean separation between minor actinides and lanthanides will be difficult to achieve using lithium drawdown.

Bayesian Optimization Analysis of Containment-Venting Operation in a Boiling Water Reactor Severe Accident

  • Zheng, Xiaoyu;Ishikawa, Jun;Sugiyama, Tomoyuki;Maruyama, Yu
    • Nuclear Engineering and Technology
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    • v.49 no.2
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    • pp.434-441
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    • 2017
  • Containment venting is one of several essential measures to protect the integrity of the final barrier of a nuclear reactor during severe accidents, by which the uncontrollable release of fission products can be avoided. The authors seek to develop an optimization approach to venting operations, from a simulation-based perspective, using an integrated severe accident code, THALES2/KICHE. The effectiveness of the containment-venting strategies needs to be verified via numerical simulations based on various settings of the venting conditions. The number of iterations, however, needs to be controlled to avoid cumbersome computational burden of integrated codes. Bayesian optimization is an efficient global optimization approach. By using a Gaussian process regression, a surrogate model of the "black-box" code is constructed. It can be updated simultaneously whenever new simulation results are acquired. With predictions via the surrogate model, upcoming locations of the most probable optimum can be revealed. The sampling procedure is adaptive. Compared with the case of pure random searches, the number of code queries is largely reduced for the optimum finding. One typical severe accident scenario of a boiling water reactor is chosen as an example. The research demonstrates the applicability of the Bayesian optimization approach to the design and establishment of containment-venting strategies during severe accidents.

THE ANALYTIC ANALYSIS OF SUPPRESSING JET FLOW AT GUIDE TUBE OF CIRCULAR IRRADIATION HOLE IN HANARO (하나로 원형 조사공의 안내관 제트유동 억제에 대한 해석)

  • Park Y.C.;Wu S.I.
    • Journal of computational fluids engineering
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    • v.10 no.2
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    • pp.1-6
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    • 2005
  • The HANARO, a multi-purpose research reactor of 30 MWth, open-tank-in-pool type, has been under normal operation since its initial criticality in February, 1995. The HANARO is composed af inlet plenum, grid plate, core channel with flow tubes and chimney. The reactor core channel is located at about twelve meters (12 m) depth of the reactor pool and cooled by the upward flow that the coolant enters the lower inlet of the plenum, rises up through the grid plate and the core channel and comes out from the outlet of chimney. A fission moly guide tube is extended from the reactor core to the top of the reactor chimney for easily loading a fission moly target under the reactor normal operation. But active coolant through the core can be quickly raised up to the top of the chimney through the guide tube by jet flow. This paper describes an analytical analysis that is the study of the flow behavior through the guide tube under reactor normal operation and unloading the target. As results, it was conformed through the analysis results that the flow rate, reduced to about fourteen kilogram per second (14 kg/s) from the original flow rate of sixteen point three kilogram per second (16.3 kg/s) did not show the guide tube jet.

Fine structure of Theileria sergenti merozoite in Korean native cattle (한우(韓牛)에 감염(感染)된 Theileria sergenti merozoite 의 미세구조(微細構造))

  • Baek, Byeong-kirl;Kim, Byeong-su;Lee, Ho-il
    • Korean Journal of Veterinary Research
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    • v.30 no.4
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    • pp.465-471
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    • 1990
  • The fine structure of the inoculated Theileria sergenti on the splenectomized Korean native cattle was observed to delineate the morphological. characteristics with transmission and scanning electron microscope. The cattle was inoculated with 1.5ml cryopreserved stabilate ($5.63{\times}10^6/{\mu}l$, PE 3%). At peak parasitemia (40%), infected blood was collected, washed and then T sergenti was observed. Scanning electron micrograph of the erythrocytes infected with T sergenti appeared various irregular from involving specific swelling, and abnormal projections like acantocyte, echinocyte and knizocyte. Transmission electron microscopic studies of T sergenti showed that piroplasm possess intracytoplasmic food vacuole, rhoptries and tubule. Merozoite, $0.6{\sim}1.81{\mu}m$ to $0.4{\sim}1.21{\mu}m$ in length, surrounded by 10~15nm thickness of pellicula. which is surrounded by a single unit membrane. Various size of veil which was observed in stroma of erythrocytes infected with T sergenti, located at the proximate part of the merozoite. The merozoite multiplied by means of binary fission so that two and more oval-like merozoites in the stroma of infected erythrocyte could be observed.

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Elemental analysis by neutron induced nuclear reaction - Nuclear track method for the analysis of fissile materials

  • Ha, Yeong-Keong;Pyo, Hyung Yeol;Park, Yong Joon;Jee, Kwang Yong;Kim, Won Ho
    • Analytical Science and Technology
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    • v.18 no.4
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    • pp.263-270
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    • 2005
  • Nuclear track is an useful tool for elemental analysis of radionuclides, such as uranium, plutonium and thorium, etc., and for elements undergoing nuclear reactions with thermal neutrons such as lithium and boron. This method has various application fields such as detecting fissionable radionuelides, measuring the fission rate in nuclear technology, analyzing cosmic radiation from meteorite, calculating the age of minerals as well as their history, etc. Track registration method has been applied to the microscopic analysis of boron and fissionable element such as uranium in KAERI. This report reviews the theoretical background of the nuclear track formation, practical procedures to obtain etched tracks and a perspective of the future.

Determination of the Neutron Effective Multiplication Factor for a PWR Spent Fuel Assembly

  • Heesung Shin;Ro, Seung-Gy;Kim, Gil-Soo;Hwang, Yong-Hwa;Kim, Ho-Dong
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.590-595
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    • 2003
  • An Exponential experiment system which is composed of a neutron detector, a signal analysis system and a neutron source, Cf-252 has been installed in order to experimentally determine the neutron effective multiplication factor for a PWR spent fuel assembly. The axial background neutron flux is measured in a preliminary performance test. From the results, the spacer grid position is determined to be consistent with the design specifications within a 2.3% relative error. The induced fission neutron for four of the assemblies is also measured by scanning the neutron source, Cf-252 or the neutron detector. The exponential decay constants have been evaluated by the application of the Poisson regression to the net induced fission neutron counts. The measured keffs determined on the basis of the exponential decay constants of Cl5 appeared to be 0.541, 0.540, 0.597 and 0.556, respectively, which are comparable with 0.55195$\pm$0.00232 of the MCNP calculation.

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Role of Chromosome Changes in Crocodylus Evolution and Diversity

  • Srikulnath, Kornsorn;Thapana, Watcharaporn;Muangmai, Narongrit
    • Genomics & Informatics
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    • v.13 no.4
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    • pp.102-111
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    • 2015
  • The karyotypes of most species of crocodilians were studied using conventional and molecular cytogenetics. These provided an important contribution of chromosomal rearrangements for the evolutionary processes of Crocodylia and Sauropsida (birds and reptiles). The karyotypic features of crocodilians contain small diploid chromosome numbers (30~42), with little interspecific variation of the chromosome arm number (fundamental number) among crocodiles (56~60). This suggested that centric fusion and/or fission events occurred in the lineage, leading to crocodilian evolution and diversity. The chromosome numbers of Alligator, Caiman, Melanosuchus, Paleosuchus, Gavialis, Tomistoma, Mecistops, and Osteolaemus were stable within each genus, whereas those of Crocodylus (crocodylians) varied within the taxa. This agreed with molecular phylogeny that suggested a highly recent radiation of Crocodylus species. Karyotype analysis also suggests the direction of molecular phylogenetic placement among Crocodylus species and their migration from the Indo-Pacific to Africa and The New World. Crocodylus species originated from an ancestor in the Indo-Pacific around 9~16 million years ago (MYA) in the mid-Miocene, with a rapid radiation and dispersion into Africa 8~12 MYA. This was followed by a trans-Atlantic dispersion to the New World between 4~8 MYA in the Pliocene. The chromosomes provided a better understanding of crocodilian evolution and diversity, which will be useful for further study of the genome evolution in Crocodylia.

An Improvement of Estimation Method of Source Term to the Environment for Interfacing System LOCA for Typical PWR Using MELCOR code

  • Han, Seok-Jung;Kim, Tae-Woon;Ahn, Kwang-Il
    • Journal of Radiation Protection and Research
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    • v.42 no.2
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    • pp.106-113
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    • 2017
  • Background: Interfacing-system loss-of-coolant-accident (ISLOCA) has been identified as the most hazardous accident scenario in the typical PWR plants. The present study as an effort to improve the knowledge of the source term to the environment during ISLOCA focuses on an improvement of the estimation method. Materials and Methods: The improvement was performed to take into account an effect of broken pipeline and auxiliary building structures relevant to ISLOCA. An estimation of the source term to the environment was for the OPR-1000 plants by MELOCR code version 1.8.6. Results and Discussion: The key features of the source term showed that the massive amount of fission products departed from the beginning of core degradation to the vessel breach. Conclusion: The release amount of fission products may be affected by the broken pipeline and the auxiliary building structure associated with release pathway.

A study on possibility of application of non-cement Hwang-to binder for Environment-friendly (친환경 무시멘트 황토결합재의 적용가능성에 관한 연구)

  • Hwang, Hey Zoo;Kang, Nam Yi
    • KIEAE Journal
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    • v.8 no.1
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    • pp.81-86
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    • 2008
  • Due to the recent environmental problems, lots of studies on the solutions to reduce the environmental pollutions are on the way. In the field of construction, concrete that we are currently consuming approximately 1 ton each year is the most common and cheap building material. We must cut down on this preoccupied use of this material and develop an alternative material as recommended by the late environmental standards. In this regard, this study propose the 'yellow soil' as the main substance that composes the final state, 'yellow soil concrete'. This study also aims to analyze the physical and chemical performances of this concrete mixed with the yellow soil by comparing it with the cement and assesses the possibility of its application to the cement. The results of the experiment shows that, assuming the solidity of the cement concrete to be around $210kg/cm^2$ (20.58MPa), the solidity of the yellow soil combined material may be around 45%~55% in terms of the range of W/B use, 200 to 400 in the per unit fission amount and less than 2% in the addition proportion of admixing agents. But the scope of the optimal concoction amount of the yellow soil concrete should better be limited as following. 40% to 50% in W/B, 300 to 400 in the per unit fission amount and less than 2% in the addition of admixing agents.

Pin Power Distribution Determined by Analyzing the Rotational Gamma Scanning Data of HANARO Fuel Bundle

  • Lee, Jae-Yun;Park, Hee-Dong
    • Nuclear Engineering and Technology
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    • v.30 no.5
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    • pp.452-461
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    • 1998
  • The pin power distribution is determined by analyzing the rotational gamma scanning data for 36 element fuel bundle of HANARO. A fission monitor of Nb$^{95}$ is chosen by considering the criteria of the half-life, fission yield, emitting ${\gamma}$-ray energy and probability. The ${\gamma}$-ray spectra were measured in Korea Atomic Energy Research Institute(KAERI) by using a HPGe detector and by rotating the fuel bundle at steps of 10$^{\circ}$. The counting rates of Nb$^{95}$ 766 keV ${\gamma}$-rays are determined by analyzing the full absorption peak in the spectra. A 36$\times$36 response matrix is obtained from calculating the contribution of each rod at every scanning angle by assuming 2-dimensional and parallel beam approximations for the measuring geometry. In terms of the measured counting rates and the calculated response matrix, an inverse problem is set up for the unknown distribution of activity concentrations of pins. To select a suitable solving method, the performances of three direct methods and the iterative least-square method are tested by solving simulation examples. The final solution is obtained by using the iterative least-square method that shows a good stability. The influences of detection error, step size of rotation and the collimator width are discussed on the accuracy of the numerical solution. Hence an improvement in the accuracy of the solution is proposed by reducing the collimator width of the scanning arrangement.

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