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Sample records for 69-group kaeri wims

  1. Honour and departure Wim Klein

    CERN Multimedia

    Van Hove,L

    1976-01-01

    L.Van Hove rend hommage à Wim Klein qui a été découvert par le Prof.Bakker vers 1958 en Hollande où Wim Klein était artiste en divertissant le public par ses extraordinaires dons mathématiques.

  2. A study for the KAERI research tunnel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J.; Hwang, Y. S.; Park, H. S.; Park, S. K.; Park, B. Y.; Bang, K. S.; Kuh, J. H.; Kang, K. H

    1997-12-01

    Major goal of the R and D on the KAERI Research Tunnel in 1997 are 1) concept development of the KAERI research tunnel and its major units 2) computer simulation of facilities 3) study on thermo-hydro mechanical coupling in the vicinity of a waste repository 4) effect of excavated distrubed zone. In addition supplementary site investigation to understand the distribution of stresses in the site was done along with long term monitoring of the water table. (author). 44 refs., 16 tabs., 36 figs

  3. The DUPIC fuel development program in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Yang, M. S.; Park, H. S. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-07-01

    This study describes the DUPIC fuel development program in KAERI as follows; Burning spent PWR fuel again in CANDU by DUPIC, Compatibility with existing CANDU system, Feasibility of DUPIC fuel fabrication, Waste reduction, Safeguard ability, Economics of DUPIC fuel cycle, The DUPIC fuel development program, and International prospective. 5 refs., 10 figs.

  4. The hydrozoan work of Prof. Wim Vervoort

    NARCIS (Netherlands)

    Cornelius, P.F.S.

    1998-01-01

    The merits of Prof. Wim Vervoort in the field of hydrozoan taxonomy are evaluated. His solid scientific approach, productivity, encyclopedic knowledge, modesty and other virtues are noted. Thanks to his work and efforts, the Nationaal Natuurhistorisch Museum at Leiden now accommodates by far the mos

  5. The technological innovation case of the KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Choi, J. I. [Habat Univ., Daejeon (Korea, Republic of); Jang, S. K. [Sungkonghoe Univ., Seoul (Korea, Republic of); Hong, K. P. [Baekseok Univ., Chunan (Korea, Republic of); Lee, E. S. [National Fusion Research Institue, Daejeon (Korea, Republic of)

    2008-01-15

    The research aims to investigate what key success factors (KSFs) of technological innovation in KAERI are, and to suggest how these findings are utilized for KAERI. In order to achieve these goals we have employed case study based on in-depth interview and literature review. And there are two fields of research in KAERI: one is nuclear energy-related research, the other is non energy-related research. The former is 'nuclear fuel cladding tube' which is an industrial product and being regarded as catch-up (or imitative) mode of technological innovation: the latter is 'HemoHIM', herbal composition of health functional food, which is consumer goods and regarded as creative (or innovative) mode of technological innovation. We found some KSFs in these two research and development cases in KAERI: firstly, to train researcher to be a 'product champion' who can fill in the gap of 'death valley' between pure research and commercialization: secondly, to build researchers' competency in order to catch up advanced countries' technological competencies. Thirdly, to amend institutional rules and regulations for commercializing processes of R and D outcomes, notably 'R and D joint venture by Government Research Institute (GRI) and private sector' fourthly, to enhance the capabilities of external management for researchers' technological innovation competency. And finally, we recommend using successful R and D cases as educational materials when training young researchers for sharing old generations' experiences and tacit knowledge.

  6. Validation of WIMS-CANDU using Pin-Cell Lattices

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Won Young; Min, Byung Joo; Park, Joo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    The WIMS-CANDU is a lattice code which has a depletion capability for the analysis of reactor physics problems related to a design and safety. The WIMS-CANDU code has been developed from the WIMSD5B, a version of the WIMS code released from the OECD/NEA data bank in 1998. The lattice code POWDERPUFS-V (PPV) has been used for the physics design and analysis of a natural uranium fuel for the CANDU reactor. However since the application of PPV is limited to a fresh fuel due to its empirical correlations, the WIMS-AECL code has been developed by AECL to substitute the PPV. Also, the WIMS-CANDU code is being developed to perform the physics analysis of the present operating CANDU reactors as a replacement of PPV. As one of the developing work of WIMS-CANDU, the U{sup 238} absorption cross-section in the nuclear data library of WIMS-CANDU was updated and WIMS-CANDU was validated using the benchmark problems for pin-cell lattices such as TRX-1, TRX-2, Bapl-1, Bapl-2 and Bapl-3. The results by the WIMS-CANDU and the WIMS-AECL were compared with the experimental data.

  7. The status of KAERI nuclear material accountancy

    Energy Technology Data Exchange (ETDEWEB)

    Park, Ho Joon; Kim, Hyun Sook; Kim, Hyun Jo; Ko, Han Suk; Lee, Byung Doo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    Nuclear material accountancy within the framework of IAEA safeguards begins with the nuclear material accounting activities by facility operators and the State system of accounting for and control of nuclear material(SSAC), implemented in accordance with the provisions of the safeguards agreement between the IAEA and the State. IAEA verify the correctness of the nuclear material accounting information in the facility records and the reports provided by the SSAC to the IAEA. This paper are described the status of KAERI nuclear material accountancy

  8. Beam Characterization at the KAERI UED Beamline

    CERN Document Server

    Setiniyaz, Sadiq; Baek, In-Hyung; Nam, Jinhee; Chae, MoonSik; Han, Byung-Heon; Gudkov, Boris; Jang, Kyu Ha; Park, Sunjeong; Miginsky, Sergey; Vinokurov, Nikolay; Jeong, Young Uk

    2016-01-01

    The UED (ultrafast electron diffraction) beamline of the KAERI's (the Korea Atomic Energy Research Institute's) WCI (World Class Institute) Center has been successfully commissioned. We have measured the beam emittance by using the quadrupole scan technique and the charge by using a novel measurement system we have developed. In the quadrupole scan, a larger drift distance between the quadrupole and the screen is preferred because it gives a better thin-lens approximation. A high bunch-charge beam, however, will undergo emittance growth in the long drift caused by the space-charge force. We present a method that mitigates this growth by introducing a quadrupole scan with a short drift and without using the thin-lens approximation. The quadrupole in this method is treated as a thick lens, and the emittance is extracted by using the thick-lens equations. Apart from being precise, our method can be readily applied without making any change to the beamline and has no need for a big drift space. For charge measure...

  9. KAERI charged particle cross section library for radioisotope production

    CERN Document Server

    Chang, J H; Kim, D H; Lee, Y O; Zhuang, Y X

    2001-01-01

    This report summarized information and figures describing the 'KAERI Charged Particle Cross Section Library for Radioisotope production' The library contains proton-, deutron-, He-3-, and alpha-induced monitor cross sections, and gamma- and positron-emitter production cross sections. Experimental data and evaluation methods are described, and the evaluated cross sections are compared with those of the IAEA, MENDL, and LA150. The library has cross sections and emission spectra suitable for the transport analysis in the design of radioisotope production system, and are available at http://atom.kaeri.re.kr/ in ENDF-6 format.

  10. The status and latest issues on KAERI export control implementation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Sook; Park, Ho Jun; Kim, Hyun Jo; Ko, Han Suk; Lee, Byung Doo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    There are four informal non-proliferation arrangements which seek to control the proliferation of weapons of mass destruction and their missile delivery systems and the transfer of conventional weapons and dual-use technologies. The four arrangements are Wassenaar Arrangement (WA) on export controls for conventional arms and dual use goods and technologies, Nuclear Supplies Group(NSG), Missile Technology Control Regime(MTCR) and Australia Group(AG) on chemical and biological weapons materials. ROK participates in four arrangements to seek to encourage responsible practice in the trade of strategic goods and technologies. It is achieved through the implementation of export control list. MKE Notification (Ministry of Knowledge Economy Notification No. 2009-250) specifies those items and technologies subject to control. In this paper, the status and latest issues on KAERI export control implementation are described

  11. DUPIC fuel fabrication using spent PWR fuels at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ho Dong; Yang, Myung Seung; Ko, Won Il and others

    2000-12-01

    This document contains DUPIC fuel cycle R and D activities to be carried out for 5 years beyond the scope described in the report KAERI/AR-510/98, which was attached to Joint Determination for Post-Irradiation Examination of irradiated nuclear fuel, by MOST and US Embassy in Korea, signed on April 8, 1999. This document is purposely prepared as early as possible to have ample time to review that the over-all DUPIC activities are within the scope and contents in compliance to Article 8(C) of ROK-U.S. cooperation agreement, and also maintain the current normal DUPIC project without interruption. Manufacturing Program of DUPIC Fuel in DFDF and Post Irradiation Examination of DUPIC Fuel are described in Chapter I and Chapter II, respectively. In Chapter III, safeguarding procedures in DFDF and on-going R and D on DUPIC safeguards such as development of nuclear material accounting system and development of containment/surveillance system are described in details.

  12. DRAGON挂载WIMS-D核数据库的基准题计算验证%Benchmark Validation of DRAGON Program Using WIMS-D Nuclear Data Library

    Institute of Scientific and Technical Information of China (English)

    杨雪; 施工; 王侃

    2007-01-01

    通过一系列基于实验的基准题对DRAGON3.05B程序挂载WIMS-D核数据库的计算结果进行验证,综合检验了其对不同燃料、不同元件结构的临界计算以及燃耗中的核密度和κ∝的计算正确性.并通过DRAGON3.05B与WIMSD-5B分别挂载WIMS-D和ENDF/B-VI.8核数据库的计算结果进行比较.结果表明:DRAGON3.05B挂载WIMS-D库的计算结果是可靠的,其正确性可以满足对钍基先进CANDU堆的设计要求.

  13. Thermal Analysis of KAERI TRISO Fuel Irradiation at HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Moon-Sung; Kim, B. G.; Yang, S. W. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The TRISO(Tri-structural Isotropic)-coated fuel particle for a VHTR has a diameter of around 1 mm, and is composed of a nuclear fuel kernel and four different outer coating layers. These coating layers consist of a buffer PyC (pyrolytic carbon) layer, an inner PyC layer, a SiC layer, and an outer PyC layer. The fuel kernel is a source of a heat generation by the nuclear fission of fissile uranium. The role of each of the four coating layers is different in view of retaining the generated fission products and other interactions during in-reactor service. KAERI has been developing a TRISO-coated particle fuel technology as a part of the Korean VHTR (Very High Temperature modular gas cooled Reactor) project, which started in 2004, and completed its first irradiation test of TRISO fuels in its research reactor, HANARO for an evaluation and prediction of the irradiation behavior of the fuel. The test was started in August 4, 2013 and finished in March 31, 2014 completing its 5 cycle irradiation of 132.2 EFPD. In this paper, thermal performance of TRISO fuels was evaluated for its five cycle irradiation at HANARO which had been carried out in the absence of the fuel temperature monitoring. A COMSOL based FE (finite element) model was utilized in this analysis. Thermal performance of TRISO fuels was evaluated for its five cycle irradiation at HANARO which had been carried out in the absence of the fuel temperature monitoring. A maximum peak temperature of 1,083 .deg. C was obtained in the rod 1 at 25.06 EFPD and the temperatures decreased as the cycle progresses.

  14. Preliminary research of CZT based PET system development in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Woo Jin; Jeong, Man Hee; Kim, Han Soo; Ha, Jang Ho [Advanced Radiation Detection Instrument and Sensor Lab., Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of); Kim, Sang Yeol [Notice Co., Ltd., Anyang (Korea, Republic of)

    2016-06-15

    For positron emission tomography (PET) application, cadmium zinc telluride (CZT) has been investigated by several institutes to replace detectors from a conventional system using photomultipliers or Silicon-photomultipliers (SiPMs). The spatial and energy resolution in using CZT can be superior to current scintillator-based state-of-the-art PET detectors. CZT has been under development for several years at the Korea Atomic Energy Research Institute (KAERI) to provide a high performance gamma ray detection, which needs a single crystallinity, a good uniformity, a high stopping power, and a wide band gap. Before applying our own grown CZT detectors in the prototype PET system, we investigated preliminary research with a developed discrete type data acquisition (DAQ) system for coincident events at 128 anode pixels and two common cathodes of two CZT detectors from Redlen. Each detector has a 19.4×19.4×6 mm{sup 3} volume size with a 2.2 mm anode pixel pitch. Discrete amplifiers consist of a preamplifier with a gain of 8 mV·fC-1 and noise of 55 equivalent noise charge (ENC), a CR-RC4 shaping amplifier with a 5 μs peak time, and an analog-to-digital converter (ADC) driver. The DAQ system has 65 mega-sample per second flash ADC, a self and external trigger, and a USB 3.0 interface.Characteristics such as the current-to-voltage curve, energy resolution, and electron mobility life-time products for CZT detectors are investigated. In addition, preliminary results of gamma ray imaging using 511 keV of a {sup 22}Na gamma ray source were obtained. In this study, the DAQ system with a CZT radiation sensor was successfully developed and a PET image was acquired by two sets of the developed DAQ system.

  15. Proceedings of the third JAERI-KAERI joint seminar on post irradiation examination technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    Between the Department of JMTR of the Japan Atomic Energy Research Institute (JAERI) and the Nuclear Fuel Cycle Research Group of the Korea Atomic Energy Research Institute (KAERI), it has been periodically carried out the collaboration on technical information exchange by specialists and scientists, under the Arrangement of the Implementation of Cooperative Research Program in the Field of Peaceful Uses of Nuclear between JAERI and KAERI. And JAERI-KAERI joint seminar has been held every three years. The 1st and 2nd JAERI-KAERI Joint Seminars were held in November 1992 at JAERI and in September 1995 at KAERI, respectively. The 3rd JAERI-KAERI Joint Seminar was held on 25 and 26 March, 1999 at the Oarai Research Establishment of JAERI. In this seminar, total participants of 84 were joined from JAERI, KAERI, Hanyang University, Japan Nuclear Cycle Development Institute, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. Contributed presentations were in three sessions; Current status and future perspectives on PIE, PIE techniques and Evaluation of PIE data. Re-assembling technique for JOYO fuel, Nd-YAG laser welding technique, grain boundary analysis using FEG-TEM, lift time estimation of PWR Rod Cluster Control Assembly (RCCA) rodlet and failure analysis of Korea Nuclear Power Plant (KNP) fuel have been widely noticed as topic items on PIE. And some comments from PIE user, were pointed out that the nano-PIE technique, the flexibility to ad-hoc demands on testing space or utilization, and the international collaboration were very important for the next generation's PIE. The 34 of the present papers are indexed individually. (J.P.N.)

  16. Status of Drum Assay System for disposal of Radioactive Waste Drums stored at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Won Hyuk; Kwak, Kyung Kil; Hong, Dae Seok; Shin, Ki Baek [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    According to the construction schedule for the final repository at Kyeong-ju in the southeast of Korea, a disposal plan for the radioactive waste drums at KAERI was required. More than 95% of all radionuclides contained in radioactive waste package should be identified for final disposal. To characterize the radioactive waste drums at KAERI, a radioactive waste drum assay facility equipped with a Wide-Range SGS system manufactured by ANTECH has been constructed. According to the acceptance criteria of KORAD and the government, KAERI make thorough preparation of disposal plan. To characterize the radioactive waste drums at KAERI, a radioactive waste drum assay facility equipped with a Wide-Range SGS system manufactured by ANTECH has been constructed. Since then, about 400 drums have been completed gamma radionuclide assay. Co-60 and Cs-137 were major radionuclides of the radioactive waste drums at KAERI. We have a plan to examine radionuclides and activity of a radioactive waste drum and secure reliability of analysis results with cross analysis using drum assay equipment at institute for inspection.

  17. Validation of WIMS-AECL reactivity device calculations for CANDU reactor

    Energy Technology Data Exchange (ETDEWEB)

    Min, Byung Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Donnelly, J. V. [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

    1997-06-01

    An important component of the overall program to validate WIMS-AECL for use with RFSP in the analysis of CANDU-6 reactors for design and safety analysis calculations is the validation of calculations of incremental cross sections used to represent reactivity devices. A method has been developed for the calculation of the three-dimensional neutron flux distribution in and around CANDU reactor fuel channels and reactivity control devices. The methods is based on one- and two dimensional transport calculations with the WIMS-AECL lattice cell code, SPH homogenization, and three-dimensional flux calculations with finite-difference diffusion theory using the MULTICELL code. Simulations of Wolsung 1 Phase-B commissioning measurements and Point Lepreau restart tests have been performed, as a part of the program to validate WIMS-AECL lattice cell calculations for application to CANDU reactor simulations in RFSP. The incremental cross section properties of the Wolsung 1 and Point Lepreau adjusters, Mechanical Control Absorbers(MCA) and liquid Zone Control Unit (ZCU) is based on the WIMS-AECL/MULTICELL modelling methods and the results are compared with those of WIMS-AECL/DRAGON-2 modelling methods. (author). 13 tabs., 4 figs., 11 refs.

  18. The KAERI 10 MeV Electron Linac - Description and Operational Manual

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Cheol; Park, Seong Hee; Jung, Young Uk; Han, Young Hwan; Kang, Hee Young

    2005-06-15

    The objective of this technical report is to guide the right operation and maintenance of the KAERI electron linac system. The KAERI electron linac system consists of 2 MeV injector based on 176 MHz Normal conducting RF (Radio Frequency)cavity and 10 MeV main accelerator based on 352 MHz Superconducting RF cavity, electron beamlines (injection and extraction). Since a electron accelerator generates hazard radiation, this system is located at the shielded room in basement and we can operate the system using the remote control system. It includes the description and the operational manual as well as the detailed technical direction for trouble shooting.

  19. Analysis of B-WIM Signals acquired in Millau Orthotropic Viaduct Using Statistical Classification

    OpenAIRE

    Ieng, Sio Song; ZERMANE, Abderraouf; Schmidt, Franziska; Jacob, Bernard

    2012-01-01

    Les systèmes B-WIM classiques sont généralement fondés sur les travaux de Moses utilisant la notion de la ligne d'influence. Ces systèmes ont été testés avec succès sur les ponts en béton à travers le monde. Ce papier s'intéresse aux travaux de recherche concernant l'utilisation d'un système B-WIM sur le viaduc de Millau qui est un pont à haubans avec une à dalle orthotrope. Nous montrons d'abord qu'un système de B-WIM ne peut pas être utilisé directement sur ce type de pont sans adaptation d...

  20. Validation of a new library of nuclear constants of the WIMS code; Validacion de una nueva biblioteca de constantes nucleares del Codigo WIMS

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F. [Departamento de Experimentacion, Gerencia del Reactor, ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-10-15

    The objective of the present work is to reproduce the experimental results of the thermal reference problems (benchmarks) TRX-1, TRX-2 and BAPL-1 to BAPL-3 with the WIMS code. It was proceeded in two stages, the first one consisted on using the original library of the code, while in the second one, a library that only contains the present elements in the benchmarks: H{sup 1}, O{sup 16}, Al{sup 27}, U{sup 235} and U{sup 238} was generated. To generate the present nuclear data in the WIMS library, it was used the ENDF/B-IV database and the Data processing system of Nuclear Data NJOY, the library was generated using the FIXER code. (Author)

  1. The Status of Development on a Web-Based Nuclear Material Accounting System at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byungdoo; Kim, Inchul; Lee, Seungho; Kim, Hyunjo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The Integrated Safeguards (IS) has been applied to 10 nuclear facilities and 1 location outside facility (LOF) at the Korea Atomic Energy Research Institute (KAERI) since July 2008. One of the major changes in the implementation of safeguards under the IS is to apply the concept of a Random Interim Inspection (RII) instead of an interim inspection. The RII plan is notified within a few hours under the IS. It is thus difficult for facility operators to prepare the inspection documents within a short time if they do not periodically manage and process the nuclear material accounting data at each facility. To resolve these issues, KAERI developed a Web-based accounting system with the function of a near real-time accounting (NRTA) system to effectively and efficiently manage the nuclear material accounting data produced at the nuclear facilities and cope with a short notice inspection under the IS, called KASIS (KAeri Safeguards Information treatment System). The facility operators must input the accounting data on the inventory changes, which are the transfers of nuclear materials among the nuclear facilities and the chemical/physical composition changes, into the KASIS. KAERI also established an RFID system for controlling and managing the transfer of nuclear material and/or radioactive materials between the nuclear facilities for the purpose of nuclear safety management, and developed the nuclear material accounting system with the functions of inventory management of nuclear material at the facility level.

  2. Status of the Decommissioning Project Management Information System Development of KAERI in 2015

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Hyung Gon; Park, Seungkook; Park, Heeseong; Song, Chanho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Various information systems have been developed and used at decommissioning sites for planning a project, record keeping for a post management and cost estimation. KAERI is the only one expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR-1 and 2 and UCP (Uranium Conversion Plant) decommission. KRR-1 and KRR-2 are TRIGA MARK type of research reactor which were constructed worldwide. Hence, there are many chance to use decommissioning experiences and data when other TRIGA MARK type of research reactors start to decommission. KAERI DPMIS stands for Decommissioning Project Management Information System, which is aiming to re-use of data effectively. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DPMIS application program, which is going to be an important mile stone of decommission industry in Korea. User friendly graphical interface and lots of actual data let people well understood on decommission planning. It is expected that continuous effort and funds will be delivered to this research.

  3. The Wim Van Leer Competition for Young Film Makers at the Jerusalem Film Festival.

    Science.gov (United States)

    Mendel, Gilli

    1999-01-01

    Describes the Jerusalem Film Center and the background, history, and organization of the Wim Van Leer Competition which was established for young filmmakers in high school. Describes the Jerusalem Film Festival, film studies programs at Israeli high schools, and future possibilities. (Author/LRW)

  4. A study on the mid- and long-term strategies of KAERI's future vision

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Maengho; Yun, S. W.; Chung, W. S.; Lee, D. S.

    2012-12-15

    In this study, KAERI's role, expected changes of KAERI's management environments and its implementational directions, strategical direction of nuclear R and D, and KAERI's future vision and sustainable growth strategies beyond the up-to date successful achievements were analysed. The purpose of this study is investigating recent rapid changes of KAERI's political and management environments to establish future vision and growth strategies of KAERI in the 21st centuries. KAERI has performed its' mission as a government funded research organization successfully and significantly contributed promotion of national nuclear industry and capabilities through manpower development and self-reliance of nuclear power technologies and academic advancement in the fields of nuclear energy. That way, it has contributed to supply stable energy and develop economy and industry as well. In order to respond properly to newly emerged missions, integral and systematic institutional efforts are required to secure more research findings from the central and local Government and industries as well. High-quality human resources having creative expertise, experiences and skills are pre-requisite for securing competitiveness of nuclear technologies and industries. So it is essential to request the Governmental support and establish the manpower development plan in long term bases. KAERI is now standing at the turning moment to take off from the catch-up strategy of the advanced nuclear technologies (KAERI 1.0) into the innovative and creative vision and challenges, that is to say, KAERI 2.0, to establish an new technological culture, respond to social requirements and seek the international leading role.

  5. Validation of WIMS-SNAP code systems for calculations in TRIGA-MARK II type reactors; Validacion del sistema de codigos WIMS-SNAP para calculos en reactores nucleares tipo TRIGA-MARK II

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez Valle, S.; Lopez Aldama, D. [Centro de Investigaciones Nucleares, Tecnologicas y Ambientales, La Habana (Cuba). E-mail: svalle@ctn.isctn.edu.cu

    2000-07-01

    The following paper contributes to validate the Nuclear Engineering Department methods to carry out calculations in TRIGA reactors solving a Benchmark. The benchmark is analyzed with the WIMS-D/4-SNAP/3D code system and using the cross section library WIMS-TRIGA. A brief description of the DSN method is presented used in WIMS/d{sup 4} code and also the SNAP-3d code is shortly explained. The results are presented and compared with the experimental values. In other hand the possible error sources are analyzed. (author)

  6. General description of KAERI LBLOCA realistic evaluation model (REM) for ECCS evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Yong; Lee, Young Jin; Chung, Bub Dong; Lee, Won Jae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-06-01

    A realistic evaluation model (REM) for LBLOCA licensing calculation is developed for application to pressurezed ligh water reactors. The developmental aim of the KAERI-REM is to provide a systematic methodology that is simple in structure and to used and built upon sound logical reasoning, for improving the code capability to realistically describe the LBLOCA phenomena and for evaluating the associated uncertainties. The method strives to be faithful to the intention of being best-estimate, that is, the method aims to evaluate the best-estimate values and the associated uncertainties while complying to the requirements in the ECCS regulations. As a demonstration, KAERI-REM was applied to quantify the safety margin for LBLOCA for Kori 3 and 4 and appended to this report. (Author) 11 refs., 2 figs., 6 tabs.

  7. Design of a Capacitive Flexible Weighing Sensor for Vehicle WIM System

    Directory of Open Access Journals (Sweden)

    Qing Li

    2007-08-01

    Full Text Available With the development of the Highway Transportation and Business Trade, vehicle weigh-in-motion (WIM technology has become a key technology and trend of measuring traffic loads. In this paper, a novel capacitive flexible weighing sensor which is light weight, smaller volume and easy to carry was applied in the vehicle WIM system. The dynamic behavior of the sensor is modeled using the Maxwell-Kelvin model because the materials of the sensor are rubbers which belong to viscoelasticity. A signal processing method based on the model is presented to overcome effects of rubber mechanical properties on the dynamic weight signal. The results showed that the measurement error is less than ���±10%. All the theoretic analysis and numerical results demonstrated that appliance of this system to weigh in motion is feasible and convenient for traffic inspection.

  8. La Escuela de Düsserdolf y el cine de Wim Wenders. The School of Düsserdolf and the cinema of Wim Wenders

    Directory of Open Access Journals (Sweden)

    Pilar Mayorgas

    2012-04-01

    Full Text Available El protagonismo de la imagen fotográfica en el cine de Wim Wenders, ya ha sido largamente estudiado, permitiéndonos un análisis aislado de la fotografía en su cine, que responda a la pregunta: qué estilo fotográfico e influencias se pueden hallar en la filmografía de Wenders. A partir de su propia auto-definición como cineasta y fotógrafo, compararemos sus imágenes, revisando las génesis y nexos que comparten, con el movimiento fotográfico de la Escuela de Düsserdolf que se construye en la misma Alemania de Wenders. Los mentores de esta Nueva Fotografía, son el matrimonio Becher: Bern y Hilla Becher iniciado en 1959, en Düsserdolf, y que junto a sus discípulos: Andreas Gursky, Candida Höfer, Thomas Struth o Thomas Ruff, colocarán a la fotografía en la primera línea del arte actual. Este hecho a un autor multidisciplinar como Wenders, no le pasará inadvertido, sino todo lo contrario; absorberá el nuevo discurso que propone esta Escuela, para exponerlo en sus tomas, revelando así en su cine una exégesis de esta nueva propuesta fotográfica en dialogo con el lenguaje cinematográfico. Todos ellos contribuirán a consolidar la imagen como arte, erigiendo al paisaje como protagonista principal.The role of the photographic image in the film by Wim Wenders has already been extensively studied, allowing us an isolated analysis of the picture at the cinema, to respond to the question: which photographic style and influences can be found in the filmography of Wim Wenders. From its own self-definition as a filmmaker and photographer, compare your images, reviewing the genesis and links that share with the movement's photographic School of Dusserdolf that is being built in the same Germany of Wim Wenders. The mentors of this new photography are marriage Becher: Bern and Hilla Becher initiated in 1959 in Dusserdolf, and that together with his disciples: Andreas Gursky, Candida Höfer, Thomas Struth or Thomas Ruff, positioned at the

  9. Wenders in Motion: A Study On The Way Of Characterization In Wim Wenders’ Road Movies

    Directory of Open Access Journals (Sweden)

    Erman Pehlivan

    2013-06-01

    Full Text Available Famous for his road movies, WimWenders, has a deeper understanding of the word; motion. More than often,Wenders tells the story of wanderers by putting them in a constant state oftravel.  These travels alter thewanderers’ characters and play a key role in Wenders’ storytelling. This paperstudies Wim Wenders’ way of characterization in three parts. The first partstates out keywords to define Wim Wenders’ wanderers: movement/motion, thejourney, homesickness, spatial levels, the Ozu connection. And it mainlyfocuses on his road trilogy: Im Lauf der Zeit (1976, FalscheBewegung (1975, and Alice in den Städten (1974, whileexplaining the stated keywords. The second part only focuses on Paris, Texas(1984 and its main character Travis, who might be seen as the ultimatewanderer whom all other Wenders’ characters blend in to. Thethird and the final part takes Der Himmel Über Berlin (1987 as ‘avertical road movie’ hoping for finding a cure for the worldwide homesicknessthat all the Wenders’ wanderers suffer.  Also there are a handful of musicreferences hidden through the paper in homage to director’s love for rock ‘n’roll music.

  10. The development of KAERI management information system -First year: The development of manpower information management system-

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Shin Bok; Huh, Young Hwan; Lee, Jong Bok; Park, Soo Jin; Lee, Young Jae; Park, Yeon Sik; Jang, Deok Kyu; Park, Seung Deok; Kim, Jong Myeong [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1991-12-01

    The purpose of this report is to describe the implementation of the management information system for manpower. This job is the first year`s for development KAERI management information system. It is important to properly manage a manpower to cope with the external circumstances promptly and to maximize the productivity of the organization. This report aims at basic management of manpower and uses multimedia to keep abreast with the times and introduces the concept of GUI (Graphic User Interface) to user for ease access. (Author).

  11. Sensitivity analysis on various parameters for lattice analysis of DUPIC fuel with WIMS-AECL code

    Energy Technology Data Exchange (ETDEWEB)

    Roh, Gyu Hong; Choi, Hang Bok; Park, Jee Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The code WIMS-AECL has been used for the lattice analysis of DUPIC fuel. The lattice parameters calculated by the code is sensitive to the choice of number of parameters, such as the number of tracking lines, number of condensed groups, mesh spacing in the moderator region, other parameters vital to the calculation of probabilities and burnup analysis. We have studied this sensitivity with respect to these parameters and recommend their proper values which are necessary for carrying out the lattice analysis of DUPIC fuel.

  12. Internal structure of spiral arms traced with [CII]: Unraveling the WIM, HI, and molecular emission lanes

    CERN Document Server

    Velusamy, T; Goldsmith, P F; Pineda, J L

    2015-01-01

    The spiral arm tangencies are ideal lines of sight in which to determine the distribution of interstellar gas components in the spiral arms and study the influence of spiral density waves on the interarm gas in the Milky Way. We present a large scale (~15deg) position-velocity map of the Galactic plane in [CII] from l = 326.6 to 341.4deg observed with Herschel HIFI. We use [CII] l-v maps along with those for Hi and 12CO to derive the average spectral line intensity profiles over the longitudinal range of each tangency. Using the VLSR of the emission features, we locate the [CII], HI, and 12CO emissions along a cross cut of the spiral arm. In the spectral line profiles at the tangencies [CII] has two emission peaks, one associated with the compressed WIM and the other the molecular gas PDRs. When represented as a cut across the inner to outer edge of the spiral arm, the [CII]-WIM peak appears closest to the inner edge while 12CO and [CII] associated with molecular gas are at the outermost edge. HI has broader ...

  13. Joint KAERI/VAEC pre-possibility study on a new research reactor for Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Park, Cheol; Lee, B. C.; Chae, H. T.; Kim, H.; Lee, C. S.; Choi, C. O.; Jun, B. J. [KAERI, Taejon (Korea, Republic of); Vien, Luong Ba; Dien, Nguyen Nhi [Vietnam Atomic Energy Commission, Hanoi (Viet Nam)

    2004-05-01

    Based on the agreement on the technical cooperation for nuclear technology between Korea and Vietnam, a KAERI/VAEC joint study on the pre-possibility of a new research reactor for Vietnam has been carried out in the research reactor area from Nov. 2003 to May 2004. In this report, the results of the pre-possibility study on a new research reactor are described. The report presents the necessity of a new research reactor in Vietnam, and the desired performance requirements of the new research reactor if necessary. The major design characteristics of some existing research reactors and those under planning were also reviewed and the main characteristics which should be considered in selecting a new multipurpose research reactor for Vietnam were drawn. Some recommendations on the considerations for the next step of the feasibility study such as the project formulation, manpower requirements and international co-operation were also briefly touched upon.

  14. Traffic weigh-in-motion (WIM measurements and validation of the Texas perpetual pavement structural design concept

    Directory of Open Access Journals (Sweden)

    Lubinda F. Walubita

    2011-01-01

    Full Text Available Over the past few years, the State of Texas has used perpetual pavement (PP structures on its heavily trafficked highways, where the expected 20-year truck-traffic estimate of 80 kN ESALs (equivalent single axle loads is in excess of 30 million. As a means to validate the Texas PP structural design concept and to make optimal future truck-traffic design recommendations, traffic Weigh In-Motion (WIM measurements were conducted and analyzed for two PP projects. The findings indicated that the initial 80 kN ESAL traffic design estimates for PP were comparable to the projections based on the actual measured WIM traffic data. However, underestimation of the hot mix asphalt layer dynamic moduli resulted in conservative designs for the PP structures. In addition, based on the successful use of the automated WIM data stations for traffic data collection, the paper highlights possible applications and advantages (as compared to conventional manual collection of traffic data of using detailed WIM traffic data information for future analyses of both highway operation and pavement structural design.

  15. Mapping Fractures in KAERI Underground Research Tunnel using Ground Penetrating Radar

    Science.gov (United States)

    Baek, Seung-Ho; Kim, Seung-Sep; Kwon, Jang-Soon

    2016-04-01

    The proportion of nuclear power in the Republic of Korea occupies about 40 percent of the entire electricity production. Processing or disposing nuclear wastes, however, remains one of biggest social issues. Although low- and intermediate-level nuclear wastes are stored temporarily inside nuclear power plants, these temporary storages can last only up to 2020. Among various proposed methods for nuclear waste disposal, a long-term storage using geologic disposal facilities appears to be most highly feasible. Geological disposal of nuclear wastes requires a nuclear waste repository situated deep within a stable geologic environment. However, the presence of small-scale fractures in bedrocks can cause serious damage to durability of such disposal facilities because fractures can become efficient pathways for underground waters and radioactive wastes. Thus, it is important to find and characterize multi-scale fractures in bedrocks hosting geologic disposal facilities. In this study, we aim to map small-scale fractures inside the KAERI Underground Research Tunnel (KURT) using ground penetrating radar (GPR). The KURT is situated in the Korea Atomic Energy Research Institute (KAERI). The survey target is a section of wall cut by a diamond grinder, which preserves diverse geologic features such as dykes. We conducted grid surveys on the wall using 500 MHz and 1000 MHz pulseEKKO PRO sensors. The observed GPR signals in both frequencies show strong reflections, which are consistent to form sloping planes. We interpret such planar features as fractures present in the wall. Such fractures were also mapped visually during the development of the KURT. We confirmed their continuity into the wall from the 3D GPR images. In addition, the spatial distribution and connectivity of these fractures are identified from 3D subsurface images. Thus, we can utilize GPR to detect multi-scale fractures in bedrocks, during and after developing underground disposal facilities. This study was

  16. Mechanical Property and Oxidation Behavior of ATF cladding developed in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il; Park, Dong-Jun; Park, Jung-Hwan; Park, Jeong-Yong; Koo, Yang-Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    To realize the coating cladding, coating material (Cr-based alloy) as well as coating technology (3D laser coating and arc ion plating combined with vacuum annealing) can be developed to meet the fuel cladding criteria. The coated Zr cladding can be produced after the optimization of coating technologies. The coated cladding sample showed the good oxidation/corrosion and adhesion properties without the spalling and/or severe interaction with the Zr alloy cladding from the various tests. Thus, it is known that the mechanical property and oxidation behavior of coated cladding concept developed in KAERI is reasonable for applying the ATF cladding in LWRs. At the present time various ATF concepts have been proposed and developing in many countries. The ATF concepts with potentially improved accident performance can be summarized to the coating cladding, Mo-Zr cladding, FeCrAl cladding, and SiCf/SiC cladding. Regarding the cladding performance, ATF cladding concepts will be evaluated with respect to the accident scenarios and normal operations of LWRs as well as to the fuel cladding fabrication.

  17. Current status of ACE format libraries for MCNP at nuclear date center of KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Do Heon; Gil, Choong Sup; Lee, Young Ouk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-09-15

    The current status of ACE format MCNP/MCNPX libraries by NDC of KAERI is presented with a short description of each library. Validation calculations with recent nuclear data evaluations ENDF/B-VII.0, ENDF/B-VII.1, JEFF-3.2, and JENDL-4.0 have been carried out by the MCNP5 code for 119 criticality benchmark problems taken from the expanded criticality validation suite supplied by LANL. The overall performances of the ACE format KN-libraries have been analyzed in comparison with the results calculated with the ENDF/B-VII.0-based ENDF70 library of LANL. It was confirmed that the ENDF/B-VII.1-based KNE71 library showed better performances than the others by comparing the RMS errors and χ2 values for five benchmark categories as well as whole benchmark problems. ENDF/B-VII.1 and JEFF-3.2 have a tendency to yield more reliable MCNP calculation results within certain confidence intervals regarding the total uncertainties for the keff values. It is found that the adoption of the latest evaluated nuclear data might ensure better outcomes in various research and development areas.

  18. First lasing of the KAERI millimeter-wave free electron laser

    Energy Technology Data Exchange (ETDEWEB)

    Lee, B.C.; Jeong, Y.U.; Cho, S.O. [Korea Atomic Energy Research Institute, Taejon (Korea, Democratic People`s Republic of)] [and others

    1995-12-31

    The millimeter-wave FEL program at KAERI aims at the generation of high-power CW laser beam with high efficiency at the wavelength of 3{approximately}10 mm for the application in plasma heating and in power beaming. In the first oscillation experiment, the FEL has lased at the wavelength of 10 mm with the pulsewidth of 10{approximately}30 {mu}s. The peak power is about 1 kW The FEL is driven by a recirculating electrostatic accelerator having tandem geometry. The energy and the current of the electron beam are 400 keV and 2 A, respectively. The FEL resonator is located in the high-voltage terminal and is composed of a helical undulator, two mesh mirrors, and a cylindrical waveguide. The parameters of the permanent-magnet helical undulator are : period = 32 mm, number of periods = 20, magnetic field = 1.3 kG. At present, with no axial guiding magnetic field only 15 % of the injected beam pass through the undulator. Transport ratio of the electron beam through the undulator is very sensitive to the injection parameters such as the diameter and the divergence of the electron beam Simulations show that, with unproved injection condition, the FEL can generate more than 50 kW of average power in CW operation. Details of the experiments, including the spectrum measurement and the recirculation of electron beam, are presented.

  19. Investigation for the Fossil Embryo using Neutron Tomography at HANARO, KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Joo; Sim, Cheul Muu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Dong Hee [National Science Museum, Daejeon (Korea, Republic of); Grellet-Tinner, Gerald [The Field Museum, Chicago (United States)

    2012-05-15

    Neutron imaging technique is one of non-destructive method. It is similar to X-ray and g-ray methods in using the different attenuation characteristics depending on materials. However, there is great difference between them. The mass attenuation coefficients of X-ray and g- ray monotonically increase with the atomic number since they interact with electrons. Thus X-ray image method does not supply sufficient contrast between similar atomic numbers. On the other hand, that of thermal neutrons depends much on the nucleus not electrons. Especially thermal neutrons easily penetrate most of metals, while they are attenuated well by such materials as hydrogen, water, boron, gadolinium and cadmium. Because of these unique characteristics of neutron, neutron imaging technique has been utilized for NDT or researches for next power sources (fuel cell or Li-Ion battery). Recently, dinosaur egg was found at the Aptian. Albian Algui Ulaan Tsav site, Mongolia. In this study, we applied the neutron imaging technique to investigate dinosaur embryo at Neutron Radiography Facility of HANARO, KAERI

  20. Validation of WIMS-AECL/(MULTICELL)/RFSP system by the results of phase-B test at Wolsung-II unit

    Energy Technology Data Exchange (ETDEWEB)

    Hong, In Seob; Min, Byung Joo; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-03-01

    The object of this study is the validation of WIMS-AECL lattice code which has been proposed for the substitution of POWDERPUFS-V(PPV) code. For the validation of this code, WIMS-AECL/(MULTICELL)/RFSP (lattice calculation/(incremental cross section calculation)/core calculation) code system has been used for the Post-Simulation of Phase-B physics Test at Wolsung-II unit. This code system had been used for the Wolsong-I and Point Lepraeu reactors, but after a few modifications of WIMS-AECL input values for Wolsong-II, the results of WIMS-AECL/RFSP code calculations are much improved to those of the old ones. Most of the results show good estimation except moderator temperature coefficient test. And the verification of this result must be done, which is one of the further work. 6 figs., 15 tabs. (Author)

  1. R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    equipped with various tools allowing it to scour surfaces, scoop samples and vacuum sludge. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extend able to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and obtaining remote situation awareness regardless of the actual task. The efficiency of the human robot interaction is very important to obtain the overall goal for the emergency response in timely manner. It would be a bottle neck to apply the robotic technology for carrying the emergency response in NPP. Simple remote operation schemes are not adequate, more intelligent autonomous operation schemes are required to enhance the effectiveness of robots for the emergency response. KAERI has been developing various robotic systems for nuclear power plants over than 20 years after the Chernobyl accident. But the majority of the developed robotic systems is for the inspection and maintenance of nuclear power plants during their outage periods. Based on the lessons learned from the Fukushima accident, KAERI has planned R and D projects for developing remote response technologies really applicable in emergency situations of nuclear facilities. This paper presents the R and D strategy to achieve real usability and the purpose and research activity plans of on going three projects derived from the strategy.

  2. Fuel burnup analysis for IRIS reactor using MCNPX and WIMS-D5 codes

    Science.gov (United States)

    Amin, E. A.; Bashter, I. I.; Hassan, Nabil M.; Mustafa, S. S.

    2017-02-01

    International Reactor Innovative and Secure (IRIS) reactor is a compact power reactor designed with especial features. It contains Integral Fuel Burnable Absorber (IFBA). The core is heterogeneous both axially and radially. This work provides the full core burn up analysis for IRIS reactor using MCNPX and WIMDS-D5 codes. Criticality calculations, radial and axial power distributions and nuclear peaking factor at the different stages of burnup were studied. Effective multiplication factor values for the core were estimated by coupling MCNPX code with WIMS-D5 code and compared with SAS2H/KENO-V code values at different stages of burnup. The two calculation codes show good agreement and correlation. The values of radial and axial powers for the full core were also compared with published results given by SAS2H/KENO-V code (at the beginning and end of reactor operation). The behavior of both radial and axial power distribution is quiet similar to the other data published by SAS2H/KENO-V code. The peaking factor values estimated in the present work are close to its values calculated by SAS2H/KENO-V code.

  3. Weighing in motion and characterization of the railroad traffic with using the B-WIM technique

    Directory of Open Access Journals (Sweden)

    J. A. DE CARVALHO NETO

    Full Text Available AbstractThe knowledge on the active moving load of a bridge is crucial for the achievement of the information on the behavior of the structure, and thus foresee maintenance, repairs and better definition of the logistics of its active vehicles. This paper presents the development of the algorithms for the application of the Bridge-Weigh In Motion (B-WIM method created by Moses for the weighing of trains during motion and also for the characterization of the rail traffic, allowing the obtainment of information like passage's train velocity and number and spacing of axles, eliminating the dynamic effect. There were implemented algorithms for the determination of the data referring to the geometry of the train and its loads, which were evaluated using a theoretical example, in which it was simulated the passage of the train over a bridge and the loads of its axles were determined with one hundred percent of precision. In addition, it was made a numerical example in finite elements of a reinforced concrete viaduct from the Carajás' Railroad, in which the developed system reached great results on the characterization and weighing of the locomotive when the constitutive equation of the Brazilian Standards was substituted by the one proposed by Collins and Mitchell.

  4. Comparison of MCNP4B and WIMS-AECL calculations of coolant-void-reactivity effects for uniform lattices of CANDU fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kozier, K.S

    1999-05-01

    This paper compares the results of coolant-void reactivity (CVR) reactor-physics calculations performed using the Monte Carlo N-particle transport code, MCNP version 4B, with those obtained using Atomic Energy of Canada Limited's (AECL's) latest version of the Winfrith improved multigroup scheme (WIMS) code, WIMS-AECL version 2-5c. Cross sections derived from the evaluated nuclear data file version B-VI (ENDF/B-VI) are used for both the WIMS-AECL and MCNP4B calculations. The comparison is made for uniform lattices at room temperature containing either fresh natural uranium or mixed oxide (MOX) 37-element CANDU fuel. The MOX fuel composition corresponds roughly to that of irradiated CANDU fuel at a burnup of about 4500 MWd/tU. The level of agreement between the CVR predictions of WIMS-AECL and MCNP4B is studied as a function of lattice buckling (a measure of the curvature of the neutron-flux distribution) over the range from 0.0 to 4.1 m{sup -2} . For the cases studied, it is found that the absolute k values calculated by WIMS-AECL are higher than those of MCNP4B by several mk (1 mk is a change of 0.001 in k), amounts that depend on the fuel type being modelled and the particular cross-section data used. However, the agreement between WIMS-AECL and MCNP4B is much better for the CVR (i.e., the {delta}k on coolant voiding), and is relatively insensitive to the fuel type. (author)

  5. Comparison of MCNP4B and WIMS-AECL calculations of coolant-void-reactivity effects for uniform lattices of CANDU fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kozier, K.S. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    1999-07-01

    This paper compares the results of coolant-void reactivity (CVR) reactor-physics calculations performed using the Monte Carlo N-particle transport code, MCNP version 4B, with those obtained using Atomic Energy of Canada Limited's (AECL's) latest version of the Winfrith improved multigroup scheme (WIMS) code, WIMS-AECL version 2-5c. Cross sections derived from the evaluated nuclear data file version B-VT (ENDF/B-VI) are used for both the WIMS-AECL and MCNP4B calculations. The comparison is made for uniform lattices at room temperature containing either fresh natural uranium or mixed oxide (MOX) 37-element CANDU fuel. The MOX fuel composition corresponds roughly to that of irradiated CANDU fuel at a burnup of about 4500 MWd/tU. The level of agreement between the CVR predictions of WIMS-AECL and MCNP4B is studied as a function of lattice buckling (a measure of the curvature of the neutron-flux distribution) over the range from 0.0 to 4.1 m{sup -2}. For the cases studied, it is found that the absolute keff values calculated by WIMS-AECL are higher than those of MCNP4B by several mk (1 mk is a change of 0.001 in keff), amounts that depend on the fuel type being modelled and the particular cross-section data used. However, the agreement between WIMS-AECL and MCNP4B is much better for the CVR (i.e., the {delta}keff on coolant voiding), and is relatively insensitive to the fuel type. (author)

  6. Investigation of the development and the effect of an excavation damaged zone at KAERI underground research tunnel

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, S.; Cho, W. J

    2008-01-15

    The understanding of the long term behavior of rock around an underground radioactive waste repository is essential for the safe design and operation of the repository and for assuring the safety and technical feasibility of geological disposal concept. The investigation of the influence of EDZ on rock mass behavior is important for the long term stability, economy, and safety points of view. In the case of underground repository, which requires high level safety criteria, the accurate prediction of the long and short term mechanical, hydraulic, and thermal behaviors is especially important. In this study, the size and characteristics of EDZ developed during the construction of the KAERI underground research tunnel, which was constructed by controlled blasting, were investigated using various methods. Goodman jack test for measuring deformation modulus, Georadar, rock core observation, MPBX, and stressmeter were carried out at KURT. The rock cores from the boreholes were tested in laboratory for estimating the EDZ size. Empirical and theoretical equations were also used for the prediction of EDZ. The results from laboratory and in situ tests were used in three-dimensional hydro-mechanical and thermo-mechanical analysis for the evaluation of the EDZ effect. The understanding of EDZ size and the property changes in EDZ from in situ and laboratory tests will be used for the planning, design, and analysis of in situ experiments in KURT. The results from the EDZ study will be helpful for the system design as well as safety analysis of a radioactive repository.

  7. A study on the impacts of R and D expenditures of Korea Atomic Energy Research Institute on the national economy. A study on the contribution made by KAERI to the national economy

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Kee Hwan; Lee, Man Ki; Song, Ki Dong; Kim, Seung Su; Lim, Chae Young [KAERI, Taejon (Korea, Republic of); Jeong, Ki Ho; Park, Sung Duk; Lee, Yo Han; Jin, Si Il; Yun, Hyun Sook; Jeong Dae Kwon [Kyungpook National Univ., Daegu (Korea, Republic of)

    2004-08-01

    This study analyzes the contribution of KAERI's R and D to the national economy. As a case study, the study also analyzes the economic impacts which KAERI's capacity of independent system design contributes to the national economy through localization of KSNP. The research method is Input-output methods which are frequently employed in evaluating economic impacts of R and D in both domestic and foreign academic areas.

  8. Modelling of 28-element UO{sub 2} flux-map critical experiments in ZED-2 using WIMS9A/PANTHER

    Energy Technology Data Exchange (ETDEWEB)

    Sissaoui, M.T.; Kozier, K.S.; Labrie, J.P. [Atomic Energy of Canada Limited (Canada)

    2011-07-01

    The accuracy of WIMS9A/PANTHER in modelling D{sub 2}O-moderated, and H{sub 2}O- or air-cooled, doubly heterogeneous lattices of fuel clusters has been demonstrated using 28-element UO{sub 2} flux-map critical experiments in the ZED-2 facility. Presented here are the predicted k{sub eff} values, coolant void reactivity biases, and the radial and axial flux shapes.

  9. Turbulent mixing in a rod bundle with vaned spacer grids: OECD/NEA–KAERI CFD benchmark exercise test

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Seok-Kyu; Kim, Seok; Song, Chul-Hwa, E-mail: chsong@kaeri.re.kr

    2014-11-15

    Highlights: • Detailed velocity profiles have been examined in a rod bundle with mixing spacer grids. • Mixing characteristics strongly depend on the type of the mixing vane on a spacer grid. • The swirl in subchannels is elliptic and the cross-flow in gaps is vigorous in the split-type. • Swirl-type vanes generate a circular swirl in a subchannel and a weak cross-flow in gaps. • Mixing performance is superior in the case of the split-type compared to the swirl-type. - Abstract: An experimental study titled the 2nd International Benchmark Exercise (IBE-2) has been conducted to provide high-precision data of detailed turbulent flow mixing in a rod bundle for validating the CFD codes being used widely in the nuclear power industry. A 5 × 5 rod bundle having mixing spacer grids was adopted as a test rig, and was contained in a square flow housing with a 170 mm side length and 4670 mm length. The 25 rods in a bundle have dimensions of 25.4 mm in outer diameter and a 3863 mm length. The benchmark experiments have been performed at the MATiS-H water loop facility in KAERI. The axial bulk velocity in a rod bundle was maintained at about 1.50 m/s (equivalent to Re ∼50,000) with loop conditions of 35 °C and 1.57 bar measured upstream of the spacer during the experiments. Detailed measurements of the turbulent flow in the subchannels were accomplished using 2-D LDA at four different distances (0.5, 1, 4 and 10 D{sub H}) from the downstream of the mixing spacer grid. The upstream flow profiles also have been measured at the inlet of the mixing spacer grid for the inlet boundary condition. Precise measurements of the lateral and axial velocities in the subchannels are presented at four downstream distances, as well as the inlet from the mixing spacer grid of two types. Turbulence intensities and vorticities in the subchannels are also evaluated from the velocity measurements.

  10. Development of the air module for the work information management system. Environmental subsystem (WIMS-ES). Master's thesis

    Energy Technology Data Exchange (ETDEWEB)

    Cantwell, R.A.; Davis, J.S.

    1992-09-01

    The primary objective of this research was to develop the air module for the Work Information Management System Environmental Subsystem (WIMSES). The air module will provide Air Force environmental managers with a management information system (MIS) to control the growing amount of air pollution data required to stay in compliance with the newly amended Clean Air Act. To develop the air module, the Air Force's air pollution management requirements were researched first. These requirements were then compared to the capabilities of existing air pollution MISs used in the Department of Defense, the Environmental Protection Agency, and in commercial industry. The research led to a draft air nodule that tracks a base's source inventory and associated permit, control equipment, and emission information. Each base's data will be fully accessible to headquarters personnel through the fully networked WIMS-ES. The draft air nodule was validated through an Air Staff review, an Air Force review, and finally, a workshop with Air Force air pollution experts. The finalized air module has been forwarded to the WIMS-ES programmers and will become the Air Force-wide air pollution MIS in early 1993.... Air pollution, Environmental management, Data management, Data bases, Management information systems, Information systems.

  11. The Potential and Beneficial Use of Weigh-In-Motion (WIM) Systems Integrated with Radio Frequency Identification (RFID) Systems for Characterizing Disposal of Waste Debris to Optimize the Waste Shipping Process

    Energy Technology Data Exchange (ETDEWEB)

    Abercrombie, Robert K [ORNL; Buckner Jr, Dooley [ORNL; Newton, David D [ORNL

    2010-01-01

    The Oak Ridge National Laboratory (ORNL) Weigh-In-Motion (WIM) system provides a portable and/or semi-portable means of accurately weighing vehicles and its cargo as each vehicle crosses the scales (while in motion), and determining (1) axle weights and (2) axle spacing for vehicles (for determination of Bridge Formula compliance), (3) total vehicle/cargo weight and (4) longitudinal center of gravity (for safety considerations). The WIM system can also weigh the above statically. Because of the automated nature of the WIM system, it eliminates the introduction of human errors caused by manual computations and data entry, adverse weather conditions, and stress. Individual vehicles can be weighed continuously at low speeds (approximately 3-10 mph) and at intervals of less than one minute. The ORNL WIM system operates and is integrated into the Bethel Jacobs Company Transportation Management and Information System (TMIS, a Radio-Frequency Identification [RFID] enabled information system). The integrated process is as follows: Truck Identification Number and Tare Weight are programmed into a RFID Tag. Handheld RFID devices interact with the RFID Tag, and Electronic Shipping Document is written to the RFID Tag. The RFID tag read by an RFID tower identifies the vehicle and its associated cargo, the specific manifest of radioactive debris for the uniquely identified vehicle. The weight of the cargo (in this case waste debris) is calculated from total vehicle weight information supplied from WIM to TMIS and is further processed into the Information System and kept for historical and archival purposes. The assembled data is the further process in downstream information systems where waste coordination activities at the Y-12 Environmental Management Waste Management Facility (EMWMF) are written to RFID Tag. All cycle time information is monitored by Transportation Operations and Security personnel.

  12. Joint research project to develop a training course or nuclear policy decision makers and planners in developing countries between KAERI and IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Suh, I. S.; Lee, H. Y. and others

    2000-12-01

    KAERI developed training course curricula on nuclear power policy and planning for decision makers and planners in developing countries under the assistance of the IAEA. It was utilized two IAEA staff members and a Korean consultation group were utilized for the development of curricula. Curriculum consists of training objectives, training contents in modular basis, detailed contents of each training module, training setting, training duration, session hours, and entry requirements of audience. One is workshop on nuclear energy policy for high-level decision makers in developing countries. The other is training course on nuclear power planning and project management for middle level managers in developing countries. The textbook in English will be printed by the end of February in 2001. Developed curricula will be implemented for Vietnam high level nuclear decision makers, middle level managers in developing countries and north Korea nuclear high level decision makers in 2001. These training courses' curricula and textbook will be utilized as basic technical documents to promote the national nuclear bilateral technical cooperation programs with Morocco, Egypt, Bangladesh, Indonesia, Ukraine, etc.

  13. L’intertexte entre le réel et l’imaginaire dans le cinéma de Wim Wenders

    Directory of Open Access Journals (Sweden)

    Gustavo Coura Guimarães Castro

    2013-04-01

    Full Text Available Cet article interroge la façon dont le cinéma représente à l’écran la frontière qui existe entre le monde imaginaire des personnages et celui qu’on appelle «monde réel». Afin de vérifier la figuration à l’écran de cette relation parfois contradictoire, voir complémentaire, on fera une brève étude du film l’Etat des Choses (1982, de Wim Wenders. Le cinéaste est né en Allemagne, en 1945. Initialement, Wenders a étudié médicine et philosophie pendant deux ans, mais, en 1967, il a changé d’avis afin de poursuivre ses études dans l’audiovisuel. A partir de là, le réalisateur s’est fait connaître comme un des représentants les plus célèbres du «nouveau cinéma allemand». En 1978, il a été invité par Francis Ford Coppola pour participer au tournage du film Hammett. Ainsi, son cinéma a été toujours marqué par cette intersection culturelle entre l’Amérique et l’Europe. Notre objectif, dans cet article, est celui de mette en évidence les croisements du cinéma avec l’art, la relation des sujets avec l’espace, ainsi que les influences d’un sur l’autre dans les représentations cinématographiques. Notre référentiel théorique sera fondé, surtout, sur les notions de «fiction» et de «documentaire» chez François Niney. Nous espérons, à partir de cette réflexion, pouvoir comprendre plus en profondeur la façon dont Wenders travaille dans son film la métaphorisation de la lumière dans les mises en scènes, en proposant, en quelque sorte, un dialogue entre les concepts de «clarté» et d’«ombre», en ayant comme arrière-plan l’idée de fiction.This article shows the way that the cinema represents on the screen the boundaries between the imaginary world of the characters and the one that we used to call “real world”. In order to verify the representation on the screen of this contradictory relationship, sometimes complementary, we will do a brief study of the movie The State

  14. 基于WIMS格式多群核数据制作过程的优化分析%Optimization analysis of the production process based on WIMS format multigroup nuclear data

    Institute of Scientific and Technical Information of China (English)

    谢明亮; 陈玉清; 于雷; 时浩

    2015-01-01

    Background:NJOY is used widely nuclear data processing program that can convert the data format of ENDF/B nuclear database into WIMS format of the multi-group cross section database.Purpose: This study aims to produce a multi-group database of WIMS-D format on the basis of the latest release of nuclear evaluation library ENDF/B-VII.1 by using nuclear data processing program NJOY-99.Methods: In allusion to basic fuel cell homogenization calculation benchmark problem of the light water reactor (LWR), taking the 235U and 238U nuclide as the main objects of analysis, the effect on processing time of making cross section library, as well as integral parametersΔKef and data sensitivity of selecting input parameters of the NJOY program were compared and analyzed, which optimized the option of input parameter. Results and Conclusion:The results of validating on benchmark problems showed that the production of the multi-group database was correct, which embodied the high accuracy of calculation and provided the basis data of fuel assembly homogenization calculation for pressurized water reactor.%基于最新释放的ENDF/B-VII.1核评价库,采用核数据加工处理程序NJOY-99制作基于WIMS格式的多群数据库,针对轻水堆(Light Water Reactor, LWR)基本燃料栅元均匀化计算基准题,以235U、238U核素为主要分析对象,对比研究了NJOY程序输入模块参数的选择对截面库制作加工时间、积分量ΔKef 及灵敏度的影响,得到优化的输入参数选择方案。基准例题验证结果表明:所制作的多群数据库是正确的,Kef 计算精度较高,可为压水堆燃料组件均匀化计算提供数据基础。

  15. Status of the atomized uranium silicide fuel development at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, C.K.; Kim, K.H.; Park, H.D.; Kuk, I.H. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-08-01

    While developing KMRR fuel fabrication technology an atomizing technique has been applied in order to eliminate the difficulties relating to the tough property of U{sub 3}Si and to take advantage of the rapid solidification effect of atomization. The comparison between the conventionally comminuted powder dispersion fuel and the atomized powder dispersion fuel has been made. As the result, the processes, uranium silicide powdering and heat treatment for U{sub 3}Si transformation, become simplified. The workability, the thermal conductivity and the thermal compatibility of fuel meat have been investigated and found to be improved due to the spherical shape of atomized powder. In this presentation the overall developments of atomized U{sub 3}Si dispersion fuel and the planned activities for applying the atomizing technique to the real fuel fabrication are described.

  16. On the structure of Lattice code WIMSD-5B

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Won Young; Min, Byung Joo

    2004-03-15

    The WIMS-D code is a freely available thermal reactor physics lattice code used widely for thermal research and power reactor calculation. Now the code WIMS-AECL, developed on the basis of WIMS-D, has been used as one of lattice codes for the cell calculation in Canada and also, in 1998, the latest version WIMSD-5B is released for OECD/NEA Data Bank. While WIMS-KAERI was developed and has been used, originated from WIMS-D, in Korea, it was adjusted for the cell calculation of research reactor HANARO and so it has no confirmaty to CANDU reactor. Therefore, the code development applicable to cell calculation of CANDU reactor is necessary not only for technological independence and but also for the establishment of CANDU safety analysis system. A lattice code WIMSD-5B was analyzed in order to set the system of reactor physics computer codes, to be used in the assessment of void reactivity effect. In order to improve and validate WIMSD-5B code, the analysis of the structure of WIMSD-5B lattice code was made and so its structure, algorithm and the subroutines of WIMSD-5B were presented for the cluster type and the pij method modelling the CANDU-6 fuel

  17. Microstructural Characterization of CdZnTe(CZT) Crystal Ingot Grown by Bridgman Method at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kyu Hong; Kim, Han Soo; Ha, Jang Ho; Kim, Young Soo; Choi, Hyo Jeong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Cd{sub 1-x}Zn{sub x}Te crystal is an important wide band-gap IIVI compound semiconductor which is one of the most attractive radiation materials for room temperature detector, especially for gamma rays. However, the electrical and radiation detection properties of CZT crystal vary widely. They have been attributed to several metallurgical defects such as dislocation, grain- and twin-boundary, Cd vacancy, and secondary phase (Te inclusion and precipitation, etc.). They act as trapping sites of carriers, and significantly degrade the detector's performance. To reduce these defects, doping elements such as Indium is applied. That method compensates Cd vacancies. In this study, 1 inch-diameter In-doped CdZnTe ingots were grown by Vertical Bridgman Method. We conducted several microstructural analyses such as Xray diffraction, edge-pit density (EPD), and ICP-MS analysis

  18. Recent Progress on Atomic Data for Fusion Plasma in KAERI Nuclear Data Center

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Duckhee; Hwang, In Hyuk; Rhee, Yongjoo; Lee, Youngouk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Atomic structure and collision cross sections are essential data for spectroscopic diagnostics of fusion plasma. We have carried out state-of-the-art calculations on cross sections for electron-impact ionization (EII) cross sections of various atoms and ions. Here we report our recent progress on those calculations and discuss future research plan focusing on the actual need for fusion plasma diagnostics. We have calculated EII cross sections of P-like ions including Fe{sup 11+}, and W ions based on a DWA. Present calculations agree with experiments better than previous other calculations. However, for lowly charged ions, our DWA calculations which uses approximated, non unitary scattering matrix have sizable discrepancies with experiments. Hence unitary corrections would be required to improve EII calculations for lowly charged ions. As well more sophisticated R matrix calculations would be required for EII of those ions in order to test DWA calculations mutually.

  19. High Power Proton Accelerator Development at KAERI and its Vacuum System

    Science.gov (United States)

    Choi, Byung-Ho; Park, Mi Young; Kim, Kui Young; Kim, Kye Ryung; Kim, Jun Yeon; Cho, Yong-Sub

    The Proton Engineering Frontier Project (PEFP), approved and launched by the Korean government in July 2002, includes a 100 MeV proton linear accelerator (linac) development and programs for its utilization and application. The main goals in the first phase of the project, spanning from 2002 to 2005, were the design of a 100 MeV proton linac and the development of a 20 MeV linac consisting of a 50 keV proton injector, a 3 MeV radio frequency quadrupole (RFQ), and a 20 MeV drift tube linac (DTL). The 50 keV injector and 3 MeV RFQ have been installed and tested, and the 20 MeV DTL is being assembled, tuned and under a beam test. At the same time, the utilization programs using the proton beam have been planned, and some are now under way. The vacuum system of the 20 MeV proton linac and its related issues, especially in operation with a high duty, are discussed in detail.

  20. Present Status and Results from the KAERI Compact THz FEL Facility

    CERN Document Server

    Jeong, Y U; Lee, B C; Park, S H

    2005-01-01

    We have developed a laboratory-scale users facility with a compact terahertz (THz) free electron laser (FEL). The FEL operates in the wavelength range of 100-1200 μm, which corresponds to 0.3-3 THz. The peak power of the FEL micropulse having 30 ps pulse duration is 1 kW and the pulse energy of the 3-μs-FEL-macropulse is approximately 0.3 mJ. The main application of the FEL is THz imaging for bio-medical researches. Transmitted THz imaging of various samples including bugs have been measured. The samples were scanned by a 2-dimensional stage at the focal point of the THz beam. The bugs were not dry because they were killed just before experiments. We could get the transmitted THz imaging of the bugs at 3 THz with the high power THz FEL. THz spectral characteristics of several materials have been studied by the FEL and a THz FTIR spectrometer. We will introduce recent results on the imaging and spectroscopy by the THz FEL.

  1. Dorstige glastuinbouw moet op elke druppel water letten (interview met Wim Voogt)

    NARCIS (Netherlands)

    Bezemer, J.; Voogt, W.

    2010-01-01

    Hoge kwaliteit water wordt schaarser. Dat dwingt de glastuinbouw zorgvuldig met de teeltfactor water om te gaan en minder afhankelijk van oppervlaktewater te worden. Hemelwater blijft de belangrijkste bron maar 100% dekking is te duur. Omgekeerde osmose blijft de meest aantrekkelijke techniek om aan

  2. Dominique Deneffe, Famke Peters and Wim Fremout, Pre-Eyckian Panel Painting in the Low Countries

    Directory of Open Access Journals (Sweden)

    2009-04-01

    Full Text Available Ce très bel ouvrage en deux volumes, publié en anglais, présente le résultat de recherches menées à l’instigation de l’IRPA et du Centre pour l’étude de la peinture du XVe siècle dans les Pays-Bas du Sud et la principauté de Liège sur un corpus d’œuvres particulières. Les panneaux peints pré-Eyckiens datant des environs de 1400 sont relativement peu nombreux : on en recense aujourd’hui une trentaine au monde. Dix d’entre eux, constituant la majeure partie des panneaux conservés en Belgique, s...

  3. Dominique Deneffe, Famke Peters and Wim Fremout, Pre-Eyckian Panel Painting in the Low Countries

    Directory of Open Access Journals (Sweden)

    Sophie Moreaux

    2009-10-01

    Full Text Available L’Institut Royal du Patrimoine Artistique et le Centre pour l’étude de la peinture du XVe siècle dans les Pays-Bas du Sud et la Principauté de Liège présentent les résultats des recherches menées sur dix oeuvres pré-eyckiennes, dans un très beau livre en deux volumes, publié en anglais. L’histoire de la peinture d’avant 1420 dans les Pays-Bas méridionaux a longtemps été teintée de légendes et de mythes persistants. Lorne Campbell, dans la préface, nous rappelle les propos de Gustave Friedrich...

  4. Soilless culture symposium (special interest for the presentations of Chris Blok and Wim Voogt)

    NARCIS (Netherlands)

    Nichols, M.; Blok, C.; Voogt, W.

    2012-01-01

    The International Symposium on Growing Media and Soilless Cultivation brought together stakeholders from around the world to address the scientific and technological advances in growing media, analytical methods and composting for horticultural uses, focusing on the sustainability of the involved pr

  5. Is Wim slim?: Samen een biogas netwerk gebruiken? : 8 december 2014

    NARCIS (Netherlands)

    Hengeveld, E.J.; Bekkering, J.; Gemert, W.J.T. van; Broekhuis, A.A.

    2014-01-01

    berekening van kosten voor biogas transport in een biogas verzamel netwerk; twee layouts worden vergeleken: de ster-layout en de visgraat-layout. Investeringen en operationele kosten, inclusief compressiekosten worden in een contante waarde berekening meegenomen. Flexigas symposium 8 december 2014

  6. Preparation macroconstants to simulate the core of VVER-1000 reactor

    Science.gov (United States)

    Seleznev, V. Y.

    2017-01-01

    Dynamic model is used in simulators of VVER-1000 reactor for training of operating staff and students. As a code for the simulation of neutron-physical characteristics is used DYNCO code that allows you to perform calculations of stationary, transient and emergency processes in real time to a different geometry of the reactor lattices [1]. To perform calculations using this code, you need to prepare macroconstants for each FA. One way of getting macroconstants is to use the WIMS code, which is based on the use of its own 69-group macroconstants library. This paper presents the results of calculations of FA obtained by the WIMS code for VVER-1000 reactor with different parameters of fuel and coolant, as well as the method of selection of energy groups for further calculation macroconstants.

  7. KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo; Kim, Jang Yeol; Eum, Heung Seop

    1997-07-01

    Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs.

  8. Progress of the Hard-wired Instrumentation and Control Works for the Neutral Beam Test Stand at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Ki Sok

    2005-12-15

    Progress of the hard-wired instrumentation and control works for the neutral beam test stand(NB-TS) has been existed for the past one year period. Details of the installed arc detector circuit are explained. LN{sub 2} level and temperature control during the cryosorption pumping operation are explained with an emphasis on its control circuit. With an expectation of more accurate and sensitive measurement of temperatures than the thermocouple utilization during the calorimeter operation, PT-100 resistance temperature detector(RTD) utilization is initiated and the results are described. During the ion beam experiment, physical measurements are made with some delayed time than the beam extraction, and thus a delayed trigger pulse generator was fabricated and installed to the system. Underlying principles of the electronic circuits for the interlock implementation and optical signal transmission are introduced. These are basically the application of operational amplifier circuits. A cautious aspect of the SMPS(switch mode power supply) utilization is also give.

  9. A Novel Approach to Find Optimized Neutron Energy Group Structure in MOX Thermal Lattices Using Swarm Intelligence

    Energy Technology Data Exchange (ETDEWEB)

    Akbari, M.; Khoshahval, F.; Minucheha, A.; Zolfaghari, A. [Shahid Beheshti Univ., Tehran (Iran, Islamic Republic of)

    2013-12-15

    Energy group structure has a significant effect on the results of multigroup transport calculations. It is known that UO{sub 2}-PuO{sub 2} (MOX) is a recently developed fuel which consumes recycled plutonium. For such fuel which contains various resonant nuclides, the selection of energy group structure is more crucial comparing to the UO{sub 2} fuels. In this paper, in order to improve the accuracy of the integral results in MOX thermal lattices calculated by WIMSD-5B code, a swarm intelligence method is employed to optimize the energy group structure of WIMS library. In this process, the NJOY code system is used to generate the 69 group cross sections of WIMS code for the specified energy structure. In addition, the multiplication factor and spectral indices are compared against the results of continuous energy MCNP-4C code for evaluating the energy group structure. Calculations performed in four different types of H{sub 2}O moderated UO{sub 2}-PuO{sub 2} (MOX) lattices show that the optimized energy structure obtains more accurate results in comparison with the WIMS original structure.

  10. A NOVEL APPROACH TO FIND OPTIMIZED NEUTRON ENERGY GROUP STRUCTURE IN MOX THERMAL LATTICES USING SWARM INTELLIGENCE

    Directory of Open Access Journals (Sweden)

    M. AKBARI

    2013-12-01

    Full Text Available Energy group structure has a significant effect on the results of multigroup transport calculations. It is known that UO2–PUO2 (MOX is a recently developed fuel which consumes recycled plutonium. For such fuel which contains various resonant nuclides, the selection of energy group structure is more crucial comparing to the UO2 fuels. In this paper, in order to improve the accuracy of the integral results in MOX thermal lattices calculated by WIMSD-5B code, a swarm intelligence method is employed to optimize the energy group structure of WIMS library. In this process, the NJOY code system is used to generate the 69 group cross sections of WIMS code for the specified energy structure. In addition, the multiplication factor and spectral indices are compared against the results of continuous energy MCNP-4C code for evaluating the energy group structure. Calculations performed in four different types of H2O moderated UO2–PuO2 (MOX lattices show that the optimized energy structure obtains more accurate results in comparison with the WIMS original structure.

  11. Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh)], E-mail: jahirulkhan@yahoo.com; Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2009-10-15

    The aim of this paper is to present the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through the analysis of the integral parameters of TRX and BAPL benchmark lattices of thermal reactors for neutronics analysis of TRIGA Mark-II Research Reactor at AERE, Bangladesh. In this process, the 69-group cross-section library for lattice code WIMS was generated using the basic evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 with the help of nuclear data processing code NJOY99.0. Integral measurements on the thermal reactor lattices TRX-1, TRX-2, BAPL-UO{sub 2}-1, BAPL-UO{sub 2}-2 and BAPL-UO{sub 2}-3 served as standard benchmarks for testing nuclear data files and have also been selected for this analysis. The integral parameters of the said lattices were calculated using the lattice transport code WIMSD-5B based on the generated 69-group cross-section library. The calculated integral parameters were compared to the measured values as well as the results of Monte Carlo Code MCNP. It was found that in most cases, the values of integral parameters show a good agreement with the experiment and MCNP results. Besides, the group constants in WIMS format for the isotopes U-235 and U-238 between two data files have been compared using WIMS library utility code WILLIE and it was found that the group constants are identical with very insignificant difference. Therefore, this analysis reflects the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through benchmarking the integral parameters of TRX and BAPL lattices and can also be essential to implement further neutronic analysis of TRIGA Mark-II research reactor at AERE, Dhaka, Bangladesh.

  12. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M., E-mail: sarker_md@yahoo.co [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2010-03-15

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k{sub eff} and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  13. The calculational VVER burnup Credit Benchmark No.3 results with the ENDF/B-VI rev.5 (1999)

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Gual, Maritza [Centro de Tecnologia Nuclear, La Habana (Cuba). E-mail: mrgual@ctn.isctn.edu.cu

    2000-07-01

    The purpose of this papers to present the results of CB3 phase of the VVER calculational benchmark with the recent evaluated nuclear data library ENDF/B-VI Rev.5 (1999). This results are compared with the obtained from the other participants in the calculations (Czech Republic, Finland, Hungary, Slovaquia, Spain and the United Kingdom). The phase (CB3) of the VVER calculation benchmark is similar to the Phase II-A of the OECD/NEA/INSC BUC Working Group benchmark for PWR. The cases without burnup profile (BP) were performed with the WIMS/D-4 code. The rest of the cases have been carried with DOTIII discrete ordinates code. The neutron library used was the ENDF/B-VI rev. 5 (1999). The WIMS/D-4 (69 groups) is used to collapse cross sections from the ENDF/B-VI Rev. 5 (1999) to 36 groups working library for 2-D calculations. This work also comprises the results of CB1 (obtained with ENDF/B-VI rev. 5 (1999), too) and CB3 for cases with Burnup of 30 MWd/TU and cooling time of 1 and 5 years and for case with Burnup of 40 MWd/TU and cooling time of 1 year. (author)

  14. Income inequality and depression: the role of social comparisons and coping resources / Ioana van Deurzen, Erik van Ingen; Wim J. H. van Oorschot

    Index Scriptorium Estoniae

    Deurzen, Ioana van

    2015-01-01

    Artiklis käsitletakse sissetulekute ebavõrdsuse ja depressiooni seoseid, pöörates tähelepanu riikidevahelistele erinevustele ja seda mõjutavatele faktoritele Euroopa riikides, sh Eesti. Aluseks on Euroopa sotsiaaluuringu (2006/2007) andmed

  15. CTcP市场商机涌动——访Punch集团贝斯印公司副总裁Wim Deblauwe先生

    Institute of Scientific and Technical Information of China (English)

    晓筠

    2005-01-01

    Punch集团继2002年4月收购了Xeikon以后,又在2004年7月收购了贝斯印,在业内引起不小反响。经过此次重组.贝斯印的CTcP技术与Punch集团下Strobbe公司的CTP技术形成一种互补。同时,重组也给贝斯印公司注入了新鲜的血液,令贝斯印能够有更充足的资金投入新技术、新产品的研发,并进一步拓展国际市场,寻求更宽广的市场空间。

  16. Deepening Exchanges and Cooperation Between Sister Cities and at Local Government Level——Speech by Wim Kok, Former Prime Minister of the Netherlands

    Institute of Scientific and Technical Information of China (English)

    2015-01-01

    First of all,being former Prime Minister of the Netherlands and on behalf of the Club de Madrid,let me thank the organizers of the 2014China International Friendship Cities Conference and Guangzhou International Urban Innovation Conference for their kind invitation and for offering the opportunity to address this very engaged and distinguished audience.The Club de Madrid is a worldwide organization that brings together nearly

  17. Immigrants' attitudes towards welfare redistribution. An exploration of role of government preferences among immigrants and natives across 18 European welfare states / Tim Reeskens, Wim van Oorschot

    Index Scriptorium Estoniae

    Reeskens, Tim

    2015-01-01

    Artiklis käsitletakse pagulaste arvamusi heaoluriigi kohta 18 Euroopa riigis (sh Eesti), täpsemalt, kuidas nad suhtuvad saadavatesse sotsiaaltoetustesse, võrreldakse ka pagulaste hoiakuid põlisrahvastiku omadega. Aluseks 2008. aasta Euroopa sotsiaaluuringu heaolu hoiakute moodul

  18. 基于 WIM 数据的上海某大桥钢箱梁应力谱研究%Fatigue Stress Spectrum Study of the Steel Box Girder of Shanghai Certain Bridge,Based on the Analysis of WIM Data

    Institute of Scientific and Technical Information of China (English)

    徐昊; 胡明敏

    2014-01-01

    斜拉桥以其自身的优点成为当今大跨度桥梁中的主流桥型,然而,投入使用一段时间后,由于运营车辆总重和交通量交替变化,钢桥所面临的疲劳问题正日趋严重。本文以上海某大桥为工程背景,利用动态称重系统采集到的车辆载荷相关数据,依据等效疲劳损伤原理,推导出代表实际运营车辆载荷谱,采用泄水法,建立南塔钢箱梁的细节应力谱,为上海某大桥疲劳损伤及寿命评估提供可靠依据。%Cable-stayed Bridge becomes the main stream bridge in the large span bridge construction because of its advantages and was built all over the world .However ,after a period of time ,the fatigue problem of the steel bridge faced with is becoming more and more serious .The representative of actual operation vehicle load spectrum is deduced with the vehicle load data collected by the dynamic weighing system and the equivalent fatigue damage theory based on the Shanghai Certain Bridge . The paper also adopted the discharge water method to build the stress spectrum of the steel box girder of The South Tower and to provide the reliable ba-sis for fatigue damage and life assessment of Shanghai Yangtze River Bridge .

  19. Validation of Decommissioning Engineering System Application against KRR-2

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Hyung Gon; Park, Seungkook; Park, Heeseong; Song, Chanho; Ha, Jaehyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant) decommission. This paper contains validation results of the KAERI DES by using KRR-2 decommissioning data. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program. One of decommissioning experience data, KRR-2 was used for KAERI DES validation and it successfully is reflected in KAERI DES.

  20. Improvement of Modeling HTGR Neutron Physics by Uncertainty Analysis with the Use of Cross-Section Covariance Information

    Science.gov (United States)

    Boyarinov, V. F.; Grol, A. V.; Fomichenko, P. A.; Ternovykh, M. Yu

    2017-01-01

    This work is aimed at improvement of HTGR neutron physics design calculations by application of uncertainty analysis with the use of cross-section covariance information. Methodology and codes for preparation of multigroup libraries of covariance information for individual isotopes from the basic 44-group library of SCALE-6 code system were developed. A 69-group library of covariance information in a special format for main isotopes and elements typical for high temperature gas cooled reactors (HTGR) was generated. This library can be used for estimation of uncertainties, associated with nuclear data, in analysis of HTGR neutron physics with design codes. As an example, calculations of one-group cross-section uncertainties for fission and capture reactions for main isotopes of the MHTGR-350 benchmark, as well as uncertainties of the multiplication factor (k∞) for the MHTGR-350 fuel compact cell model and fuel block model were performed. These uncertainties were estimated by the developed technology with the use of WIMS-D code and modules of SCALE-6 code system, namely, by TSUNAMI, KENO-VI and SAMS. Eight most important reactions on isotopes for MHTGR-350 benchmark were identified, namely: 10B(capt), 238U(n,γ), ν5, 235U(n,γ), 238U(el), natC(el), 235U(fiss)-235U(n,γ), 235U(fiss).

  1. Comparison of neutron cross sections for selected fission products and isotopic composition analyses with burnup

    Energy Technology Data Exchange (ETDEWEB)

    Kim, D. H.; Gil, C. S.; Kim, J. D.; Jang, J. H.; Lee, Y. D. [KAERI, Taejon (Korea)

    2003-10-01

    The neutron absorption cross sections for 18 fission products evaluated within the framework of the KAERI-BNL international collaboration have been compared with the ENDF/B-VI release 7. Also, the influence of the new evaluations on isotopic compositions of the fission products as a function of burnup has been analyzed through the OECD/NEA burnup credit criticality benchmarks (Phase 1B) and the LWR/Pu recycling benchmarks. These calculations were performed by WIMSD-5B with the 69 group libraries prepared from three evaluated nuclear data libraries: ENDF/B-VI.7, ENDF/B-VI.8 including new evaluations in resonance region covering thermal region, and ENDF/B-VII expected including those in upper resonance region up to 20 MeV. For Xe-131, the composition calculated with ENDF/B-VI.8 shows maximum difference of 4.78% compared to ENDF/B-VI.7. However, the isotopic compositions of all fission products calculated with ENDF/B-VII shows no differences compared to ENDF/B-VI.7.

  2. Comparisons of Neutron Cross Sections and Isotopic Composition Calculations for Fission-Product Evaluations

    Science.gov (United States)

    Kim, Do Heon; Gil, Choong-Sup; Chang, Jonghwa; Lee, Yong-Deok

    2005-05-01

    The neutron absorption cross sections for 18 fission products evaluated within the framework of the KAERI (Korea Atomic Energy Research Institute)-BNL (Brookhaven National Laboratory) international collaboration have been compared with ENDF/B-VI.7. Also, the influence of the new evaluations on the isotopic composition calculations of the fission products has been estimated through the OECD/NEA burnup credit criticality benchmarks (Phase 1B) and the LWR/Pu recycling benchmarks. These calculations were performed by WIMSD-5B with the 69-group libraries prepared from three evaluated nuclear data libraries: ENDF/B-VI.7, ENDF/B-VI.8 including the new evaluations in the resonance region covering the thermal region, and the expected ENDF/B-VII including those in the upper resonance region up to 20 MeV. For Xe-131, the composition calculated with ENDF/B-VI.8 shows a maximum difference of 5.02% compared to ENDF/B-VI.7. However, the isotopic compositions of all the fission products calculated with the expected ENDF/B-VII show no differences when compared to ENDF/B-VI.7 for the thermal reactor benchmark cases.

  3. Evaluation of significance of Zr bound in ZrH{sub x} for its possible inclusion in the WIMSD-5 cross section library

    Energy Technology Data Exchange (ETDEWEB)

    Bhyuian, S.I.; Sarker, M.M.; Chakrobortty, T.K.; Khan, M.J.H. [Institute of Nuclear Science and Technology, AERE, Dhaka, (Bangladesh); Kulikowska, Teresa [Institute of Atomic Energy, Swierk, Otwock (Poland)

    2001-03-01

    The principal objective of this study was to evaluate the significance of a separate data for Zirconium bound in Zirconium hydride rather than as a free atom and its possible inclusion in the WIMSD library. A TRIGA research reactor benchmark input specified for WIMSD-5 was prepared. The calculations have been performed by the WIMSD-5B code and the ANL version of WIMSD code. In the ANL version, two sets of data for Hydrogen were available: for Hydrogen bound in water and Hydrogen bound in Zirconium hydride. For Zirconium, the available data were for Zirconium natural and Zirconium bound in Zirconium hydride prepared without taking into account the P{sub 1} correction. A separate data for Zirconium bound for Zirconium hydride with P{sub 1} correction was prepared for the WIMSD-5B code at INST, AERE, Savar. The cross section data for all the elements of the benchmark input have been processed by NJOY94.10+ based on ENDF/B-VI library and incorporated in the 69-group WIMS library. All the calculations have been carried out applying 69 energy groups in the main transport routine with subsequent condensation to 7 group. Four cases namely (i) diffusion, (ii) B{sub 1} with P{sub 1} thermal scattering matrices for H and O in water only, (iii) as above but with a P{sub 1} matrix also for H bound in ZrHx, (iv) as above but with a P{sub 1} matrix also for Zr bound in ZrHx were studied. It is seen that the differences in cross sections are negligible although the overall effect in K-eff is up to 700 pcm in the case of ANL, and in our case, the effect is even stronger. The possible cause of this inconsistency could be the absence of P{sub 1} matrices for all the principal materials for the benchmark input in the WIMSD library. The author of the WIMS recommends the usage of P{sub 1} matrices only if they are available for all principal isotopes of a material. No material is treated separately on the level of leakage calculations and the contribution from the first order is

  4. Pre-test analysis of an integral effect test facility for thermal hydraulic similarities of 6 inches cold leg break and DVI line break using MARS-1D

    Energy Technology Data Exchange (ETDEWEB)

    Ah, D. J.; Park, H. S.; Choi, K. Y.; Kwon, T. S.; Baek, W. P. [KAERI, Taejon (Korea, Republic of)

    2002-05-01

    Pre-test analyses of a small-break loss-of-coolant accident (SBLOCA) and a DVI line break accident, have been performed for the integral effect test loop of Korea Atomic Energy Research Institute (KAERI-ITL), the construction of which will be started soon. The KAERI-ITL is being designed with a full-height and 1/310 volume scale based on the design features of the APR1400 (Korean Next Generation Reactor). Based on the same control logics and accident scenarios, the similarity between the KAERI-ITL and the prototype plant, APR1400, is evaluated using the MARS code. It is found that the KAERI-ITL and APR1400 have similar thermal hydraulic responses during the transient under the identical accident scenarios. It is also verified that the volume scaling law, applied to the design of the KAERI-ITL, gives reasonable results to keep the similarity between APR1400 and KAERI-ITL.

  5. Development of chemical flocculant for wastewater treatment

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jang Jin; Shin, J. M.; Lee, H. H.; Kim, M. J.; Yang, M. S.; Park, H. S

    2000-12-01

    Reagents 'KAERI-I and KAERI-II' which were developed as coagulants for industrial wastewater treatment in the study showed far superior performance to the existing inorganic coagulants such as Alum and Iron salt(FeSO4) when compared to their wastewater treatment performance in color and COD removal. Besides, it was not frozen at -25 deg C {approx} -30 deg C. When reagents 'KAERI-I and KAERI-II' were used as coagulant for wastewater treatment, the proper dosage was ranged from 0.1% to 0.5%(v/v) and proper pH range was 10.5 {approx} 11.5 in the area of alkaline pH.Reagents 'KAERI-I and KAERI-II' showed good performance with 95% or more removal of color-causing material and 60% or more removal of COD.

  6. Adapting and implementing the Wine in Moderation-Art de Vivre programme in Argentina

    Directory of Open Access Journals (Sweden)

    Alvarez Natalia

    2014-01-01

    Full Text Available The Wine in Moderation-Art de Vivre (WIM programme was officially launched in 2008 as the wine sector's contribution to the EU Alcohol & Health Forum, within the framework of the EU strategy to support Member States in reducing alcohol-related harm. Building on the values of the “wine culture” and founded on information backed by science, broad education & self-regulation, WIM aims at promoting moderate and responsible behavior in the consumption of wine as a social and cultural norm. Considering the global and national trends in the wine market, the drinking patterns and the alcohol & health policy, Bodegas de Argentina (BAAC decided to mobilize concrete actions to contribute to the reduction of alcohol related harm, by adapting and implementing the WIM programme in Argentina. BAAC decided to engage the whole national wine value chain in the WIM programme and empower them with necessary knowledge and tools to properly implement it and disseminate the WIM message. The first step was to adapt the WIM programme and message to the cultural and linguistic context respecting the programme's common approach and creating an action plan with 2 main phases. With the Argentinean wine value chain participating in WIM and having the proper skills to do, the challenge now lies in reaching consumer. The successful implementation in Argentina has set a milestone in WIM's international development.

  7. Hybrid bayesian networks for traffic load models from weigh-in-motion data

    NARCIS (Netherlands)

    Morales-Nápoles, O.; Steenbergen, R.D.J.M.

    2012-01-01

    The Weigh-in-Motion (WIM) systems are used, among other applications, in pavement and bridge engineering, in infrastructure monitoring and assessment and inspection and reinforcement strategies. In the Netherlands and some other countries, the video-WIM system was implemented for pre-selection, and

  8. Description and user manual of the WIMSLIC, FIXER and COMPA programs; Descripcion y manual del usuario de los programas WIMSLIC, FIXER y COMPA

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1992-08-15

    In this work the WIMS library and those WIMSLIC, FIXER and COMPA codes that are used to give him maintenance or to create a new one, the way to use them and its scopes are described. The objective of WIMSLIC, is the one of generating data nuclear with the WIMS code format, uses those results obtained with the NJOY system and the one POWR module, the FIXER function is to generate a new WIMS library or to already modify an existent, using the results of the one WIMSLIC code or those obtained with NJOY and WIMSR, while the COMPA function is to compare data groups with WIMS format. In the Appendix 1 the files of data are had that would use to generate a new library of WIMS that contain nuclear data for U-235, U-238, H-1, 0-16 and Al-27. In the Appendix 2 one has the listing of the programs before mentioned. (Author)

  9. Proliferation-resistant stable isotope separation based on optical pumping

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Cheol-Jung; Park, Hyunmin; Ko, Kwang-Hoon; Lim, Gwon; Kim, Taek-Soo; Rho, Sipyo; Cha, Yong-Ho; Han, Jamin; Jeong, Do-Young [Korea Atomic Energy Research Institute, Deajeon (Korea, Republic of). Quantum Optics Division

    2008-07-01

    Korea Atomic Energy Research Institute (KAERI) has developed the laser stable isotope separation based on optical pumping which can be applied to isotopes with small isotopic shift, provides high enrichment, is economical owing to high efficiency, and is proliferation-resistant. KAERI's laser isotope separation is based on isotope-selective optical pumping by very narrow bandwidth continuous wave laser followed by efficient infrared photo-ionization. KAERI demonstrated the pilot production of Tl-203 enriching over 97 % and separating 100 mg/hr. KAERI also demonstrated the separation of Yb-168 over 30 % and Yb- 176 over 97 % with tens of mg/hr. KAERI plans to scale up the production of Tl-203 up to 500 mg/hr and apply it to separation of Zn-67, Zn-70, Ba-130 and Ca-48 which are very important in medical industry and basic sciences. (author)

  10. Automatic Traffic Recorder (ATR) Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  11. Water Well Locations - MO 2012 Certified Wells (SHP)

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This data set provides information about wells that are certified by the State of Missouri. The parent data set is the Wellhead Information Management System (WIMS)...

  12. Paris, Texas. Saksamaal ja sinu peas / Kairi Prints

    Index Scriptorium Estoniae

    Prints, Kairi

    2010-01-01

    6.- 12. oktoobrini Tallinnas ja Tartus toimuval filmifestivalil "Uus Saksa Kino" saab vaadata Wim Wendersi muusikadokumentaale. "Film ja filosoofia" rubriigis koha- ja rahvusespetsiifika eksistentsist tänapäeva filmikunstis ja W. Wendersi filmist "Paris, Texas" (USA 1984)

  13. Film Premiere: Arrows of time at exploratorium

    CERN Multimedia

    2007-01-01

    "Join award-wimming artist and filmmaker Ken McMullen for a uniqude presentation of films engaging ideas at the forefront of science and culture on Sunday, Apri 29 at 2pm at the Exploratorium." (1/3 page)

  14. SPS tunnels fill up

    CERN Multimedia

    1974-01-01

    Here the installation of a 25 tons beam dump. Wim Middelkoop stands near the wall (2nd on the left); Peter Sievers stands on the left behind the magnet; Eric Geiger is 3rd along the wall on the right.

  15. Teel tagasi laste juurde / Jaak Lõhmus

    Index Scriptorium Estoniae

    Lõhmus, Jaak

    2005-01-01

    Cannes'i 58. filmifestivalilt : Jean-Pierre ja Luc Dardenne'i "Laps" ("L'Enfant"), Jim Jarmuschi "Murtud lilled" ("Broken Flowers"), Wim Wendersi "Ära tule koputama" ("Don't Come Knocking"), Michael Haneke "Varjatud" ("Cache")

  16. Weigh-in-Motion Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  17. WW - ajakirjanik, publitsist / Linnar Priimägi

    Index Scriptorium Estoniae

    Priimägi, Linnar, 1954-

    1998-01-01

    Wim Wendersi dokumentaalfilmist "Ülestähendustest riiete ja linnade kohta" ("Aufzeichnungen zu Kleidern und Städten") : Saksamaa 1989. Selles filmis intervjueerib ja portreteerib režissöör jaapani moeloojat Yohji Yamamotot

  18. Development of DUPIC safeguards neutron counter

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Gil; Cha, Hong Ryul; Kim, Ho Dong; Hong, Jong Sook; Kang, Hee Young

    1999-08-01

    KAERI, in cooperation with LANL, developed DSNC (DUPIC Safeguards Neutron Counter) for safeguards implementing on DUPIC process which is under development by KAERI for direct use of spent PWR fuel in CANDU reactors. DSNC is a well-type neutron coincidence counter with substantial shielding to protect system from high gamma radiation of spent fuel. General development procedures in terms of design, manufacturing, fabrication, cold and hot test, performance test for DSNC authentication by KAERI-IAEA-LANL are described in this report. It is expected that the techniques related DSNC development and associated neutron detection and evaluation method could be applied for safeguards improvement. (Author). 20 refs., 16 tabs. 98 figs.

  19. Participation in the 1999 IAEA interlaboratory comparison on chemical analysis of groundwater

    Energy Technology Data Exchange (ETDEWEB)

    Joe, Kih Soo; Choi, Kwang Soon; Han, Sun Ho; Suh, Moo Yul; Park, Kyung Kyun; Choi, Ke Chun; Kim, Won Ho

    2000-08-01

    KAERI analytical laboratory participated in the 1999 IAEA interlaboratory comparison on chemical analysis of groundwater organized by IAEA Hydrology Laboratory(RAS/8/084). 13 items such as pH, electroconductivity, HCO{sub 3}, Cl, SO{sub 4}, NO{sub 3}, SiO{sub 2}, B, Li, Na, K, Ca, Mg were analyzed. The result of this program showed that KAERI laboratory was ranked within 10% range from top level. An analytical expert in KAERI attended the 'Consultants' Meeting' at IAEA headquater and prepared the guideline for chemical analysis of groundwater.

  20. Preclinical Study for Application of Fabricated High Activity Ir-192

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Mi Son; Kang, Seung Hee; Oh, Young Taek; Jeong, Chul; Kim, Mi Hwa; Hwang, Jeong Hye; Kim, Hee Seong; Im, Eun Jeong [Ajou University, Suwon (Korea, Republic of)

    2005-10-15

    This study was performed to evaluate the feasibility and safety of high activity Ir-192 sources manufactured by KAERI(Korea Atomic Energy Research Institute) for application to present equipment such as various applicators inserted to patients and PLATO(Nucletron, Netherland) of treatment planning system and to evaluate safety and accuracy of Ir-192 as practical clinic use through in vitro dosimetry of Ir-192. We confirmed the physical and radiobiological safety of KAERI sources to use practical. KAERI sources are applicable to commercial high dose rate brachytherapy machine safely. Then those can be substituted for the imported sources such as sources made by Nucletron, Gammamed and exported to the foreign country

  1. CANDU RU fuel manufacturing basic technology development and advanced fuel verification tests

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chang Hwan; Chang, S.K.; Hong, S.D. [and others

    1999-04-01

    A PHWR advanced fuel named the CANFLEX fuel has been developed through a KAERI/AECL joint Program. The KAERI made fuel bundle was tested at the KAERI Hot Test Loop for the performance verification of the bundle design. The major test activities were the fuel bundle cross-flow test, the endurance fretting/vibration test, the freon CHF test, and the fuel bundle heat-up test. KAERI also has developing a more advanced PHWR fuel, the CANFLEX-RU fuel, using recovered uranium to extend fuel burn-up in the CANDU reactors. For the purpose of proving safety of the RU handling techniques and appraising feasibility of the CANFLEX-RU fuel fabrication in near future, a physical, chemical and radiological characterization of the RU powder and pellets was performed. (author). 54 refs., 46 tabs., 62 figs.

  2. Fabrication of a CANFLEX-RU designed bundle for power ramp irradiation test in NRU

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Moon Sung

    2000-11-01

    The BDL-443 CANFLEX-RU bundle AKW was fabricated at Korea Atomic Energy Research Institute (KAERI) for power ramp irradiation testing in NRU reactor. The bundle was fabricated with IDR and ADU fuel pellets in adjacent elements and contains fuel pellets enriched to 1.65 wt% {sup 235}U in the outer and intermediate rings and also contains pellets enriched to 2.00 wt% {sup 235}U in the inner ring. This bundle does not have a center element to allow for insertion on a hanger bar. KAERI produced the IDR pellets with the IDR-source UO{sub 2} powder supplied by BNFL. ADU pellets were fabricated and supplied by AECL. Bundle kits (Zircaloy-4 end plates, end plugs, and sheaths with brazed appendages) manufactured at KAERI earlier in 1996 were used for the fabrication of the bundle. The CANFLEX bundle was fabricated successfully at KAERI according to the QA provisions specified in references and as per relevant KAERI drawings and technical specification. This report covers the fabrication activities performed at KAERI. Fabrication processes performed at AECL will be documented in a separate report.

  3. ORNL Automated-In-Motion Evaluation Environment (AIMVEE) User Training and Testing Materials - U.S. Copyright TXu 1-797-273

    Energy Technology Data Exchange (ETDEWEB)

    Abercrombie, Robert K [ORNL; Sheldon, Frederick T [ORNL

    2012-01-01

    The AIMVEE/WIM system electronically retrieves deployment information, identifies vehicle automatically, and determines total weight, individual wheel weight, individual axle weights, axle spacing, and center-of-balance for any wheeled vehicle in motion. The AIMVEE/WIM system can also perform these functions statically for both wheel vehicles and cargo with information. The AIMVEE/WIM system incorporates digital images and applies cubing algorithms to determine length, width, height for cubic dimensions of both vehicle and cargo. Once all this information is stored, it electronically links to data collection and dissemination systems to provide actual weight and measurement information for planning, deployment, and in-transit visibility. The Static Scale Conversion (SSC) system is an unique enhancement to the AIMVEE/WIM system. It enables a SSC to weigh and measure vehicles and cargo dynamically (i.e., as they pass over the large scale and is included in the AIMVEE computer code base. The material copyrighted is the ORNL Automated-In-Motion Vehicle Evaluation Environment (AIMVEE)/Weigh-In-Motion User Training and Testing material. It includes instructional material in the set-up, operation and tear-down of the AIMVEE/WIM system. It also includes a final exam associated with the training.

  4. Use of Finite Elements Analysis for a Weigh-in-Motion Sensor Design

    Directory of Open Access Journals (Sweden)

    Viorel Goanta

    2012-05-01

    Full Text Available High speed weigh-in-motion (WIM sensors are utilized as components of complex traffic monitoring and measurement systems. They should be able to determine the weights on wheels, axles and vehicle gross weights, and to help the classification of vehicles (depending on the number of axles. WIM sensors must meet the following main requirements: good accuracy, high endurance, low price and easy installation in the road structure. It is not advisable to use cheap materials in constructing these devices for lower prices, since the sensors are normally working in harsh environmental conditions such as temperatures between –40 °C and +70 °C, dust, temporary water immersion, shocks and vibrations. Consequently, less expensive manufacturing technologies are recommended. Because the installation cost in the road structure is high and proportional to the WIM sensor cross section (especially with its thickness, the device needs to be made as flat as possible. The WIM sensor model presented and analyzed in this paper uses a spring element equipped with strain gages. Using Finite Element Analysis (FEA, the authors have attempted to obtain a more sensitive, reliable, lower profile and overall cheaper elastic element for a new WIM sensor.

  5. The Vertical Structure of Warm Ionised Gas in the Milky Way

    CERN Document Server

    Gaensler, B M; Chatterjee, S; Mao, S A

    2008-01-01

    We present a new joint analysis of pulsar dispersion measures and diffuse H-alpha emission in the Milky Way, which we use to derive the density, pressure and filling factor of the thick disk component of the warm ionised medium (WIM) as a function of height above the Galactic disk. By excluding sightlines at low Galactic latitude that are contaminated by HII regions and spiral arms, we find that the exponential scale-height of free electrons in the diffuse WIM is 1830 (+120, -250) pc, a factor of two larger than has been derived in previous studies. The corresponding inconsistent scale heights for dispersion measure and emission measure imply that the vertical profiles of mass and pressure in the WIM are decoupled, and that the filling factor of WIM clouds is a geometric response to the competing environmental influences of thermal and non-thermal processes. Extrapolating the properties of the thick-disk WIM to mid-plane, we infer a volume-averaged electron density 0.014 +- 0.001 cm^-3, produced by clouds of ...

  6. Improving the efficiency of weigh in motion systems through optimized allocating truck checking oriented procedure

    Directory of Open Access Journals (Sweden)

    Abbas Mahmoudabadi

    2013-03-01

    Full Text Available In the present paper, an effective procedure is proposed to determine the best location(s for installing Weigh in Motion systems (WIM. The main objective is to determine locations for best performance, defined as the maximum number of once-checked trucks' axle loads and minimizing unnecessary actions. The aforesaid method consists of two main stages, including solving shortest path algorithm and selecting the best location for installing WIM(s. A proper mathematical model has also been developed to achieve objective function. The number of once-checked trucks, unnecessary actions and average installing costs are defined as criteria measures. The proposed procedure was applied in a road network using experimental data, while the results were compared with the usual methods of locating enforcement facilities. Finally, it is concluded that the proposed procedure seems to be more efficient than the traditional methods and local experts' points of view.

  7. Analysis of benchmarks on the reactivity temperature coefficient using new libraries based on ENDF/B-VI (release 5) and JEF2-2 data

    Energy Technology Data Exchange (ETDEWEB)

    Erradi, L.; Htet, A.; Chakir, E

    2001-06-01

    This paper presents, the analysis of discrepancies between calculation and experiments in the prediction of isothermal moderator temperature coefficient of a set of lattice experiments, using WIMSD4, WIMSD5B and APOLLO1 lattice codes. In this analysis we have used the original cross sections libraries (CEA-86 library for APOLLO1 and both of 1981 and 1986 libraries for WIMS) and the updated ones based on JEF2.2 data for APOLLO code and both of ENDF/B6 and JEF2.2 data for WIMS code. We have also analysed the numerical benchmark proposed by Mosteller to evaluate the accuracy in predicting Doppler coefficient in light water type lattices. This study on Doppler coefficient was performed using, in addition to APOLLO and WIMS codes, the Monte Carlo code MCNP4B for which a new library based on ENDF/B6 nuclear data file, have been processed using the NJOY system.

  8. Analysis of benchmarks on the reactivity temperature coefficient using new libraries based on ENDF/B-VI (release 5) and JEF2-2 data

    CERN Document Server

    Erradi, L; Chakir, E

    2001-01-01

    This paper presents, the analysis of discrepancies between calculation and experiments in the prediction of isothermal moderator temperature coefficient of a set of lattice experiments, using WIMSD4, WIMSD5B and APOLLO1 lattice codes. In this analysis we have used the original cross sections libraries (CEA-86 library for APOLLO1 and both of 1981 and 1986 libraries for WIMS) and the updated ones based on JEF2.2 data for APOLLO code and both of ENDF/B6 and JEF2.2 data for WIMS code. We have also analysed the numerical benchmark proposed by Mosteller to evaluate the accuracy in predicting Doppler coefficient in light water type lattices. This study on Doppler coefficient was performed using, in addition to APOLLO and WIMS codes, the Monte Carlo code MCNP4B for which a new library based on ENDF/B6 nuclear data file, have been processed using the NJOY system.

  9. Optic Fiber-Based Dynamic Pressure Sensor

    Institute of Scientific and Technical Information of China (English)

    Jiu-Lin Gan; Hai-Wen Cai; Jian-Xin Geng; Zheng-Qing Pan; Rong-Hui Qu; Zu-Jie Fang

    2008-01-01

    Weigh-in-Motion(WIM) technique is the process of measuring the dynamic tire forces of a moving vehicle and estimating the corresponding tire loads of the static vehicle. Compared with the static weigh station, WIM station is an efficient and cost effective choice that will minimize unneccessary stops and delay for truckers. The way to turn birefringence of single-mode fiber into a prime quality for a powerful and reliable sensor is shown. Preliminary results for the development of a weigh-in-motion (WIM) technique based on sagnac-loop sensor are presented. After a brief description of the sensor and its principle of operation, the theoretical model is developed. Then, a full characterization made in static conditions is presented.

  10. ZigBee-based wireless multi-sensor system for physical activity assessment.

    Science.gov (United States)

    Mo, Lingfei; Liu, Shaopeng; Gao, Robert X; John, Dinesh; Staudenmayer, John; Freedson, Patty

    2011-01-01

    Physical activity (PA) is important for assessing human exposure to the environment. This paper presents a ZigBee-based Wireless wearable multi-sensor Integrated Measurement System (WIMS) for in-situ PA measurement. Two accelerometers, a piezoelectric displacement sensor, and an ultraviolet (UV) sensor have been used for the physical activity assessment. Detailed analysis was performed for the hardware design and embedded program control, enabling efficient data sampling and transmission, compact design, and extended battery life to meet requirements for PA assessment under free-living conditions. Preliminary testing of the WIMS has demonstrated the functionality of the design, while performance comparison of the WIMS with a wired version on an electromagnetic shaker has demonstrated the signal validity.

  11. FLYSAFE, nowcasting of in flight icing supporting aircrew decision making process

    Science.gov (United States)

    Drouin, A.; Le Bot, C.

    2009-09-01

    FLYSAFE is an Integrated Project of the 6th framework of the European Commission with the aim to improve flight safety through the development of a Next Generation Integrated Surveillance System (NGISS). The NGISS provides information to the flight crew on the three major external hazards for aviation: weather, air traffic and terrain. The NGISS has the capability of displaying data about all three hazards on a single display screen, facilitating rapid pilot appreciation of the situation by the flight crew. Weather Information Management Systems (WIMS) were developed to provide the NGISS and the flight crew with weather related information on in-flight icing, thunderstorms, wake-vortex and clear-air turbulence. These products are generated on the ground from observations and model forecasts. WIMS supply relevant information on three different scales: global, regional and local (over airport Terminal Manoeuvring Area). Within the flysafe program, around 120 hours of flight trials were performed during February 2008 and August 2008. Two aircraft were involved each with separate objectives : - to assess FLYSAFE's innovative solutions for the data-link, on-board data fusion, data-display, and data-updates during flight; - to evaluate the new weather information management systems (in flight icing and thunderstorms) using in-situ measurements recorded on board the test aircraft. In this presentation we will focus on the in-flight icing nowcasting system developed at Météo France in the framework of FLYSAFE: the local ICE WIMS. The local ICE WIMS is based on data fusion. The most relevant information for icing detection is extracted from the numerical weather prediction model, the infra-red and visible satellite imagery and the ground weather radar reflectivities. After a presentation of the local ICE WIMS, we detail the evaluation of the local ICE WIMS performed using the winter and summer flight trial data.

  12. An outstanding guest

    CERN Multimedia

    2004-01-01

    The person celebrating CERN's 25th anniversary whose photograph we published last week was not just any guest. Readers have pointed out that it was Wim Klein, whose remarkable abilities are part of CERN's history. Well known as one of the best "human calculators", Wim was recruited by CERN in 1957 to verify computer programs, which at the time were still stumbling. Moreover, he regularly beat their speed in calculating and gave breath-taking demonstrations. During one such demonstration in September 1973, he calculated the 19th root of a 133-digit number in less than 2 minutes !

  13. 公共的价值 比利时根特市政厅

    Institute of Scientific and Technical Information of China (English)

    Marie-Jose Van Hee Robbrecht

    2013-01-01

    工程名称:比利时根特市市政厅坐落地点:比利时根特 参与设计:Jan Baes, Tom Broes, Bert Callens, Katrien Cammers, Axel Clissen, Mattias Deboutte, Petra Decouttere, Ame Deruyter Linde Everaerd, Trice Hofkens, Gert Jansseune. Daniel Libens. Wim Menten, Carmen Osten, Filip Reumers, Sofie Reynaert, Miriam Rohde, Johannes Robbrecht, Marilu Sicoli, Gert Swolfs, Pieter Vanderhoydonck, Kathy Vermeeren Caroline Voet, Wim Watschap竣工时间:2012摄影:NickHufton

  14. Improving truck safety: Potential of weigh-in-motion technology

    Directory of Open Access Journals (Sweden)

    Bernard Jacob

    2010-07-01

    Full Text Available Trucks exceeding the legal mass limits increase the risk of traffic accidents and damage to the infrastructure. They also result in unfair competition between transport modes and companies. It is therefore important to ensure truck compliance to weight regulation. New technologies are being developed for more efficient overload screening and enforcement. Weigh-in-Motion (WIM technologies allow trucks to be weighed in the traffic flow, without any disruption to operations. Much progress has been made recently to improve and implement WIM systems, which can contribute to safer and more efficient operation of trucks.

  15. New generation polyphase resonant converter-modulators for the Korean atomic energy research institute

    Energy Technology Data Exchange (ETDEWEB)

    Reass, William A [Los Alamos National Laboratory; Baca, David M [Los Alamos National Laboratory; Gribble, Robert F [Los Alamos National Laboratory

    2009-01-01

    This paper will present operational data and performance parameters of the newest generation polyphase resonant high voltage converter modulator (HVCM) as developed and delivered to the KAERI 100 MeV ''PEFP'' accelerator [1]. The KAERI design realizes improvements from the SNS and SLAC designs [2]. To improve the IGBT switching performance at 20 kHz for the KAERI system, the HVCM utilizes the typical zero-voltage-switching (ZVS) at turn on and as well as artificial zero-current-switching (ZCS) at turn-off. The new technique of artificial ZCS technique should result in a 6 fold reduction of IGBT switching losses (3). This improves the HCVM conversion efficiency to better than 95% at full average power, which is 500 kW for the KAERI two klystron 105 kV, 50 A application. The artificial ZCS is accomplished by placing a resonant RLC circuit across the input busswork to the resonant boost transformer. This secondary resonant circuit provides a damped ''kick-back'' to assist in IGBT commutation. As the transformer input busswork is extremely low inductance (< 10 nH), the single RLC network acts like it is across each of the four IGBT collector-emitter terminals of the H-bridge switching network. We will review these topological improvements and the overall system as delivered to the KAERI accelerator and provide details of the operational results.

  16. Fabrication of CANFLEX bundle kit for irradiation test in NRU

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Moon Sung; Kwon, Hyuk Il; Ji, Chul Goo; Chang, Ho Il; Sim, Ki Seob; Suk, Ho Chun

    1997-10-01

    CANFLEX bundle kit was prepared at KAERI for the fabrication of complete bundle at AECL. Completed bundle will be used for irradiation test in NRU. Provisions in the `Quality Assurance Manual for HWR Fuel Projects,` `Manufacturing Plan` and `Quality Verification, Inspection and Test Plan` were implemented as appropriately for the preparation of CANFLEX kit. A set of CANFLEX kit consist of 43 fuel sheath of two different sizes with spacers, bearing pads and buttons attached, 2 pieces of end plates and 86 pieces of end caps with two different sizes. All the documents utilized as references for the fabrication such as drawings, specifications, operating instructions, QC instructions and supplier`s certificates are specified in this report. Especially, suppliers` certificates and inspection reports for the purchased material as well as KAERI`s inspection report are integrated as attachments to this report. Attached to this report are supplier`s certificates and KAERI inspection reports for the procured materials and KAERI QC inspection reports for tubes, pads, spacers, buttons, end caps, end plates and fuel sheath. (author). 37 refs.

  17. Development of Voloxidation Process for Treatment of LWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. J.; Jung, I. H.; Shin, J. M. (and others)

    2007-08-15

    The objective of the project is to develop a process which provides a means to recover fuel from the cladding, and to simplify downstream processes by recovering volatile fission products. This work focuses on the process development in three areas ; the measurement and assessment of the release behavior for the volatile and semi-volatile fission products from the voloxidation process, the assessment of techniques to trap and recover gaseous fission products, and the development of process cycles to optimize fuel cladding separation and fuel particle size. High temperature adsorption method of KAERI was adopted in the co-design of OTS for hot experiment in INL. KAERI supplied 6 sets of filter for hot experiment. Three hot experiment in INL hot cell from the 25th of November for two weeks with attaching 4 KAERI staffs had been carried out. The results were promising. For example, trapping efficiency of Cs was 95% and that of I was 99%, etc.

  18. The study for the high qualification of international nuclear training

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Byong Chull; Kim, Hyun Jin

    2012-12-15

    It is suggested how to reach high qualification of KAERI international nuclear training and how to play a leading role for new paradigm on the international training on the world. 1. The formulation of the core nuclear training framework- The systematic formulation of nuclear training framework based on the existing turning course design 2. Planning and operation of KAERI- Excellent Technology Series training course- The advertisement for KAERI Excellent Technology through the continuous international training and the future market development on the world for the nuclear technology 3. e-Learning training contents development- e-Learning training contents development to play a leading role for new training paradigm on the world and to overcome the limit of time/spacy.

  19. The operational procedure of an electron beam accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Cheol; Choi, Hwa Lim; Yang, Ki Ho; Han, Young Hwan; Kim, Sung Chan

    2008-12-15

    The KAERI(Korea Atomic Energy of Research Institute) high-power electron beam irradiation facility, operating at the energies between 0.3 MeV and 10 MeV, has provided irradiation services to users in industries, universities, and institute in various fields. This manual is for the operation of an electron beam which is established in KAERI, and describes elementary operation procedures of electron beam between 0.3 Mev and 10 MeV. KAERI Electron Accelerator facility(Daejeon, Korea) consists of two irradiators: one is a low-energy electron beam irradiator operated by normal conducting RF accelerator, the other is medium-energy irradiator operated by superconducting RF accelerator. We explain the check points of prior to operation, operation procedure of this facility and the essential parts of electron beam accelerator.

  20. A Procedure for Determination of Degradation Acceptance Criteria for Structures and Passive Components in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J.; Braverman, J.; Hofmayer, C.; Choun, Y-S.; Hahm, D.; Choi, I-K.

    2012-01-30

    The Korea Atomic Energy Research Institute (KAERI) has been collaborating with Brookhaven National Laboratory since 2007 to develop a realistic seismic risk evaluation system which includes the consideration of aging of structures and components in nuclear power plants (NPPs). This collaboration program aims at providing technical support to a five-year KAERI research project, which includes three specific areas that are essential to seismic probabilistic risk assessment: (1) probabilistic seismic hazard analysis, (2) seismic fragility analysis including the effects of aging, and (3) a plant seismic risk analysis. The understanding and assessment of age-related degradations of structures, systems, and components and their impact on plant safety is the major goal of this KAERI-BNL collaboration. Four annual reports have been published before this report as a result of the collaboration research.

  1. Development of Silver-exchanged Adsorbents for the Removal of Fission Iodine from Alkaline Dissolution

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Taewoon; Lee, Seung-Kon; Lee, Suseung; Lee, Jun Sig [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Most of the iodine exists in the caustic dissolution as iodide form. KAERI is developing LEU-based fission 99 Mo production process which is connected to the new research reactor, which is being constructed in Kijang, Busan, Korea. In KAERI process, silver-exchanged adsorbent is used to adsorb iodide from the solution. Adsorbed iodide can be recovered and recycled for radiopharmaceuticals. In KAERI process, silver-exchanged adsorbent is used to adsorb iodide from the solution. Adsorbed iodide can be recovered and recycled for radiopharmaceuticals. Synthesis of silver-doped alumina is conducted in two ways. One is using the ascorbic acid as a reducing agent. However, this method is impossible to control.

  2. Development of Nuclear Control and Management Information Treatment System

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, J. G.; Lee, B. D.; So, D. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    To implement obligations under the Non-Proliferation Treaty (NPT) and the bilateral agreements more effectively, we proposed a computerized system named the Nuclear Control and Management Information Treatment System (NCAMITS) as a part of the Nuclear Transparency Enhancement Project at the Korea Atomic Energy Research Institute (KAERI). The database system is designed not only to undertake the facility-level accounting for and control of nuclear material at KAERI, but also to meet the requirements of the State (National) System of Accounting and Control (SSAC). Since the NCAMITS will provide services for the facility operators as well as the safeguard information managers at KAERI, the development of the system is supposed to accommodate the end-user's convenience and the manager's sophisticated specifications as well.

  3. Optimum nuclear design of target fuel rod for Mo-99 production in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myung Hyun [Kyung Hee University, Seoul (Korea)

    1998-04-01

    Nuclear target design for Mo-99 production in HANARO was performed, KAERI proposed target design was analyzed and its feasibility was shown. Three commercial target designs of Cintichem, ANL and KAERI were tested for the HANARO irradiation an d they all satisfied with design specification. A parametric study was done for target design options and Mo-99 yields ratio and surface heat flux were compared. Tested parameters were target fuel thickness, irradiation location, target axial length, packing density of powder fuel, size of target radius, target geometry, fuel enrichment, fuel composition, and cladding material. Optimized target fuel was designed for both LEU and HEU options. (author). 17 refs., 33 figs., 42 tabs.

  4. Establishment of QA system for ACP hot cell demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, K. S.; Nam J. H.; Jeo, I. J.; Lim, N. J.; Jeong, W. M.; Koo, J. H.; Kook, D. H.; Park, S. W. [KAERI, Taejon (Korea)

    2003-10-01

    The Advanced spent fuel Conditioning Process(ACP), which is being developed by KAERI, is now in the 2nd research phase. This phase has a goal to design the total system of active demonstration of ACP. The facilities for the ACP process demonstration will be constructed by some modification works of the future hot cell located at the basement floor of IMEF in KAERI. The QA system for the ACP Hot Cell demonstration was established in the 1st year in the 2nd research phase and have been utilized in the remain two years, and will be also utilized in construction and process demonstration periods in the 3rd research phase.

  5. Glass fiber-reinforced polymer packaged fiber Bragg grating sensors for low-speed weigh-in-motion measurements

    Science.gov (United States)

    Al-Tarawneh, Mu'ath; Huang, Ying

    2016-08-01

    The weight of rolling trucks on roads is one of the critical factors for the management of road networks due to the continuous increase in truck weight. Weigh-in-motion (WIM) sensors have been widely used for weight enforcement. A three-dimensional glass fiber-reinforced polymer packaged fiber Bragg grating sensor (3-D GFRP-FBG) is introduced for in-pavement WIM measurement at low vehicle passing speed. A sensitivity study shows that the developed sensor is very sensitive to the sensor installation depth and the longitudinal and transverse locations of the wheel loading position. The developed 3-D GFRP-FBG sensor is applicable for most practical pavements with a panel length larger than 6 ft, and it also shows a very good long-term durability. For the three components in 3-D of the developed sensor, the longitudinal component has the highest sensitivity for WIM measurements, followed by the transverse and vertical components. Field testing validated the sensitivity and repeatability of the developed 3-D GFRP-FBG sensor. The developed sensor provides the transportation agency one alternative solution for WIM measurement, which could significantly improve the measurement efficiency and long-term durability.

  6. Englemøtet over Berlin

    DEFF Research Database (Denmark)

    Ørjasæter, Kristin

    2006-01-01

    This reading of Dag Solstads novel 16.07.41 (2002) is focussed on the presentation of Berlin in the text. The article also a discusses the angel-theme that can be find in this novel as well as in Wim Wenders Der himmel über Berlin (1987)....

  7. Quantification of Uncertainty in the Remedial Investigation/Feasibility Studies Process

    Science.gov (United States)

    1993-09-01

    converted into a spreadsheet using the Ixcel "Parse" comnand. 41 Quantification of uncertainty could not be done with the WIMS-ES data for three reasons...and Data Handled Program Office. There he developed computerized financial management for the Satellite Control Network . Captain Held entered the

  8. Groen mbo niet nodig voor groene carrière : onderzoekers in kritisch essay (interview met W. de Jong)

    NARCIS (Netherlands)

    Boetzkes, P.; Jong, de L.W.

    2011-01-01

    Het groen mbo heeft in zijn huidige vorm onvoldoende meerwaarde voor de arbeidsmarkt in de tuinbouw, agro & food. Vooral waar het uitvoerend werk betreft. Daarom kan de overheid het extra geld dat ze erin steekt beter anders investeren. Dat stelt onderzoeker Wim de Jong.

  9. NOWCASTING OF IN-FLIGHT hazard thunderstorm, supporting aircrew and ATM decision making process

    Science.gov (United States)

    Guillou, Y.; Senesi, S.; Tafferner, A.; Forster, C.

    2009-09-01

    The Integrated Project FLYSAFE allows to define and experiment Weather Information Management Systems (WIMS). These systems provide met data on several weather hazards: icing, clear air turbulence and thunderstorms. The thunderstorm system, called CB WIMS (Cb for Cumulonimbus), has been developed with involvement of partners from Météo-France, German Aerospace Center (DLR), ONERA, UK-Met Office and the University of Hannover. In order to reduce the complexity of a real thunderstorm to a practical model which can be used onboard aircraft for informing pilot of hazard area, it is been represented as bottom and top hazard volumes. The bottom volumes are defined from ground RADAR network and has two levels of hazard severity. The top volume is defined on satellite data and includes only one level of hazard severity. In this presentation, we will focus on test flights operated during summer campaign in August 2008, and more precisely on flights operated by the research plane of Météo-France (ATR42). Through different case studies, we will point out the important contribution of CB WIMS to complete the pilot view of thunderstorm hazards which is available from the single board RADAR. Indeed, in addition to an overview of thunderstorm hazard, the CB WIMS provide relevant information on thunderstorm evolution too. The bottom volume can also indicate hazard area in lower layers not necessary detected by onboard radar but which can result in a moderate turbulence for the plane.

  10. Ion-Neutral Collisions in the Interstellar Medium: Wave Damping and Elimination of Collisionless Processes

    Science.gov (United States)

    Spangler, Steven R.; Savage, Allison H.; Redfield, Seth

    2011-09-01

    Most phases of the interstellar medium contain neutral atoms in addition to ions and electrons. This introduces differences in plasma physics processes in those media relative to the solar corona and the solar wind at a heliocentric distance of 1 astronomical unit. In this paper, we consider two well-diagnosed, partially-ionized interstellar plasmas. The first is the Warm Ionized Medium (WIM) which is probably the most extensive phase in terms of volume. The second is the gas of the Local Clouds of the Very Local Interstellar Medium (VLISM). Ion-neutral interactions seem to be important in both media. In the WIM, ion-neutral collisions are relatively rare, but sufficiently frequent to damp magnetohydrodynamic (MHD) waves (as well as propagating MHD eddies) within less than a parsec of the site of generation. This result raises interesting questions about the sources of turbulence in the WIM. In the case of the VLISM, the ion-neutral collision frequency is higher than that in the WIM, because the hydrogen is partially neutral rather than fully ionized. We present results showing that prominent features of coronal and solar wind turbulence seem to be absent in VLISM turbulence. For example, ion temperature does not depend on ion mass. This difference may be due to ion-neutral collisions, which distribute power from more effectively heated massive ions such as iron to other ion species and neutral atoms.

  11. Access, Equity, and Opportunity. Women in Machining: A Model Program.

    Science.gov (United States)

    Warner, Heather

    The Women in Machining (WIM) program is a Machine Action Project (MAP) initiative that was developed in response to a local skilled metalworking labor shortage, despite a virtual absence of women and people of color from area shops. The project identified post-war stereotypes and other barriers that must be addressed if women are to have an equal…

  12. Our Hitler - A Film by Hans-Jürgen Syberberg

    NARCIS (Netherlands)

    Elsaesser, T.; Machtans, K.; Ruehl, M.A.

    2012-01-01

    A good deal of the interest aroused by the so-called New German Cinema in the 1970s and 1980s was generated by the impression - as well as the expectation - that the films of Werner Herzog, Rainer Werner Fassbinder, Hans-Jürgen Syberberg, Wim Wenders, and others were not just another European new wa

  13. Analysis of axle and vehicle load properties through Bayesian networks based on weigh-in-motion data

    NARCIS (Netherlands)

    Morales Napoles, O.; Steenbergen, R.D.J.M.

    2014-01-01

    Weigh-in-Motion (WIM) systems are used, among other applications, in pavement and bridge reliability. The system measures quantities such as individual axle load, vehicular loads, vehicle speed, vehicle length and number ofaxles. Because ofthe nature ofúamc configuration, the quantities measured are

  14. Rock-hard coatings

    NARCIS (Netherlands)

    Muller, M.

    2007-01-01

    Aircraft jet engines have to be able to withstand infernal conditions. Extreme heat and bitter cold tax coatings to the limit. Materials expert Dr Ir. Wim Sloof fits atoms together to develop rock-hard coatings. The latest invention in this field is known as ceramic matrix composites. Sloof has sign

  15. 妙用imagex快速给Vista减肥

    Institute of Scientific and Technical Information of China (English)

    俞木发

    2007-01-01

    第1步把Vista安装光盘中的install.wim文件复制到“e:\\”下,然后启动命令提示符窗口,执行命令“imagex/apply e:\\install.wim 1 j:\\vista”,将install.wim的第一部分提取到j:\\vista下。

  16. Näitused / Mari Sobolev

    Index Scriptorium Estoniae

    Sobolev, Mari, 1968-

    1998-01-01

    Tallinna XI graafikatriennaal. Rotermanni soolaladu: "Puudutus"; Kunstihoone: "Puutujad"; Rahvusraamatukogu: Laste ja noorte graafikanäitus; Kastellaanimaja galerii: Wim Lamboo (s. 1949) "Eesti kunstnike portreed 1997" (fotograafia); Tallinna Botaanikaaed: "Maised rõõmud"; Rahvusraamatukogu: Antanas Sutkus (s. 1939) "Pro memoria" (fotograafia); Tammsaare majamuuseum: Eve Pärnaste "Ülelend" (maalid); Haapsalu Linnagalerii: Paul Allik "Seisundid" (aktimaalid).

  17. An Assessment of Resonance Treatment in WIMSD-5B

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Won Young; You, Guk Jong; Min, Byung Joo; Park, Joo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    WIMSD-5B is a lattice code with a depletion capability for the analysis of reactor physics problems related to a design and safety. It is released from the OECD/NEA Data Bank in 1998 and is now being used widely for thermal research and power reactor calculations. The purpose of this study is to assess and improve the resonance treatment method in WIMSD- 5B, through the introduction of a new method with a high accuracy in treating the resonance, as one of the development works for WIMS/CANDU, which is being developed for replacing WIMS-AECL, for the physics analysis of CANDU reactors. In this article, we specifically describe the recent improvements in the resonance integral method using the Carlvik's approximation. As a result, a comparison for the resonance calculation on the CANDU-6 fuel lattice was performed between the WIMSD-5B code and the WIMS/CANDU code with the 69-energy groups of the ENDF/B-VI nuclear data library and the WIMS-AECL code with the 89-energy group of the ENDF/B-VI nuclear data library.

  18. Progress on Developing an Interface Program between WIMSD-5B and RFSP

    Energy Technology Data Exchange (ETDEWEB)

    You, Guk Jong; Kim, Won Young; Park, Joo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    WIMS (Winfrith Improved Multigroup Scheme) code is a multi-group transport code for the reactor lattice calculations which includes a fuel depletion or burn-up routine. The code, created at the United Kingdom Atomic Energy Authority Establishment, Winfrith (AEEW), was intended to perform the lattice calculations with an acceptable accuracy for the analysis of the experiments in a wide range of geometries. As one of its branches, WIMSD-5B is a code which was released from OECD/NEA Data Bank in 1998 and now has been used widely for thermal research and power reactor calculation. Also one of WIMS codes, WIMS-AECL, has been developed by AECL in Canada as an independent version of the original AEEW code. While WIMS-AECL produces a data file which can generate the information required by other code such as RFSP, WIMSD-5B does not. The data file is used for the reactor analysis by WIMSAECL in connection with RFSP. This study is to develop an interface data file (Tape 16) of WIMSD-5B with RFSP and to develop a process utility to provide the group collapsing and cell average cross-section generation for a CANDU-6 core analysis on the WINDOW system. With this utility, the physics analysis of a CANDU-6 reactor will be performed by RFSP code using the lattice parameters generated by WIMSD-5B.

  19. Interface Screenings

    DEFF Research Database (Denmark)

    Thomsen, Bodil Marie Stavning

    2015-01-01

    In Wim Wenders' film Until the End of the World (1991), three different diagrams for the visual integration of bodies are presented: 1) GPS tracking and mapping in a landscape, 2) video recordings layered with the memory perception of these recordings, and 3) data-created images from dreams...

  20. Atheïstische religiositeit : Een pragmatische analyse in de geest van William James, Erich Fromm en Leo Apostel

    NARCIS (Netherlands)

    Moer, Van Wim

    2012-01-01

    Atheïsme en religiositeit lijken elkaars absolute tegenpolen. Filosoof Wim Van Moer stelt deze intuïtieve, ook onder atheïsten wijdverspreide overtuiging ter discussie. Deze analyse onthult dat de religieuze ervaring niet verbonden hoeft te zijn met een geloof in een bovennatuurlijke entiteit of rea

  1. Nomads and Monads

    DEFF Research Database (Denmark)

    van der Meijden, Peter Alexander

    The dissertation describes and analyses Fluxus acivities in Germany, Denmark and Holland during the period 1962-66. Its protagonists are Tomas Schmit, Wolf Vostell and Joseph Beuys (Germany), Arthur Køpcke, Eric Andersen and Henning Christiansen (Denmark) and Willem de Ridder and Wim T. Schippers...

  2. Eestlased kaotasid Telekomi aktsiatega kaks ja pool miljardit / Erkki Erilaid

    Index Scriptorium Estoniae

    Erilaid, Erkki

    2001-01-01

    Eesti Telekomi aktsia püstitas uue odavusrekordi, kukkudes päevaga 6,35% 44,25 kroonini. Diagramm: Eesti Telekom taas rekordmadal. Vt. samas: Kangus, Aivo. Rasked valikud. Arvamust avaldavad: Wim Duisenberg, Siim Kallas ja Horst Koehler

  3. The wisconsin Ha mapper: a new look at the warm ionized medium

    Directory of Open Access Journals (Sweden)

    L. M. Haffner

    2000-01-01

    Full Text Available El relevamiento en H-Alpha de Wisconsin (WHAM ha cubierto todo el cielo del norte en H desde Kitt Peak, Arizona. Usando un espectr ometro Fabry-Perot de alta transmisividad, con etal on doble de 15 cm y un CCD de alta sensibilidad, el relevamiento WHAM ha obtenido el primer mapa con velocidades calibradas en H en emisi on de nuestra Galaxia. Una zona amplia, que incluye el brazo Local (Ori on y el brazo de Perseo, tambi en ha sido observada por el WHAM en las l neas de [S II] y [N II]. Estos nuevos datos muestrean directamente y por primera vez, las condiciones f sicas a gran escala del medio ionizado tibio (WIM. Las tendencias de los cocientes de l neas sugieren que las variaciones en la temperatura son muestreadas por los mapas de [N II]/H y [S II]/H . Dado que estos cocientes se incrementan fuertemente en regiones alejadas del plano Gal actico, revelan un incremento sustancial en la temperatura del WIM del halo. Adem as de este resultado, los datos revelan una nueva region H II excitada por una estrella B, dan una medida de la escala de altura de los electrones del WIM y, del cociente [S II]/[N II], proveen nueva informaci on sobre la ionizaci on del WIM.

  4. Excitation of the diffuse ionized gas in galaxies

    Directory of Open Access Journals (Sweden)

    Crystal L. Martin

    2000-01-01

    Full Text Available Se revisan las propiedades del gas ionizado difuso (DIG en galaxias cercanas con formaci on estelar, enfatizando la evidencia para un mecanismo de excitaci on adicional a la fotoionizaci on estelar. Discuto la pregunta frecuentemente hecha sobre si el DIG en galaxias externas es similar al medio ionizado tibio (WIM descrito en esta reuni on por Reynolds y Ha ner.

  5. Notitie over het uitplanten van korstmossen

    NARCIS (Netherlands)

    Geraerdts, W.H.J.M.; Ketner-Oostra, H.G.M.

    2006-01-01

    In de voormalige tuin van Wim Geraedts (Wijchen, Gelderland) blijkt het uitplanten van korstmossen een sukses te zijn. Het gaat om enkele Cladonia-soorten, een Cladina- en twee Peltigera-soorten. Het biotoop waarin ze uitgezet zijn, ligt op een wal van heideplaggen om een kunstmatig hoogveentje met

  6. A Look at Psychometrics in the Netherlands.

    Science.gov (United States)

    Hambleton, Ronald K.; Swaminathan, H.

    Comments are made on the review papers presented by six Dutch psychometricians: Ivo Molenaar, Wim van der Linden, Ed Roskam, Arnold Van den Wollenberg, Gideon Mellenbergh, and Dato de Gruijter. Molenaar has embraced a pragmatic viewpoint on Bayesian methods, using both empirical and pure approaches to solve educational research problems. Molenaar…

  7. Sorteerwater gereinigd met ozon

    NARCIS (Netherlands)

    PPO Fruit,

    2009-01-01

    Energie uit de lucht wordt het tegenwoordig ook wel genoemd. Futuroloog Wim de Ridder weet het zeker : uit zonne-energie gehaalde elektriciteit wordt steeds goedkoper. Over zo'n tien jaar komt er een omslag en wordt het mogelijk stroom voor een habbekrats te produceren

  8. The relationship between fatty acid profiles in milk identified by Fourier transform infrared spectroscopy and onset of luteal activity in Norwegian dairy cattle.

    Science.gov (United States)

    Martin, A D; Afseth, N K; Kohler, A; Randby, Å; Eknæs, M; Waldmann, A; Dørum, G; Måge, I; Reksen, O

    2015-08-01

    To investigate the feasibility of milk fatty acids as predictors of onset of luteal activity (OLA), 87 lactations taken from 73 healthy Norwegian Red cattle were surveyed over 2 winter housing seasons. The feasibility of using frozen milk samples for dry-film Fourier transform infrared (FTIR) determination of milk samples was also tested. Morning milk samples were collected thrice weekly (Monday, Wednesday, Friday) for the first 10 wk in milk (WIM). These samples had bronopol (2-bromo-2-nitropropane-1,3-diol) added to them before being frozen at -20°C, thawed, and analyzed by ELISA to determine progesterone concentration and the concentrations of the milk fatty acids C4:0, C14:0, C16:0, C18:0, and cis-9 C18:1 as a proportion of total milk fatty acid content using dry-film FTIR, and averaged by WIM. Onset of luteal activity was defined as the first day that milk progesterone concentrations were >3 ng/mL for 2 successive measurements; the study population was categorized as early (n=47) or late (n=40) OLA, using the median value of 21 DIM as the cutoff. Further milk samples were collected 6 times weekly, from morning and afternoon milkings, these were pooled by WIM, and one proportional sample was analyzed fresh for fat, protein, and lactose content by the dairy company Tine SA, using traditional FTIR spectrography in the wet phase of milk. Daily energy-balance calculations were performed in 42 lactations and averaged by WIM. Animals experiencing late OLA had a more negative energy balance in WIM 1, 3, 4, and 5, with the greatest differences been seen in WIM 3 and 4. A higher proportion of the fatty acids were medium chained, C14:0 and C16:0, in the early than in the late OLA group from WIM 1. In WIM 4, the proportion of total fatty acid content that was C16:0 predicted late OLA, with 74% sensitivity and 80% specificity. The long-chain proportion of the fatty acids C18:0 and cis-9 C18:1 were lower in the early than in the late OLA group. Differences were greatest in

  9. Maintenance and fabrication of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chong Eun; Moon, Byung Soo; Hong, Suk Boong; Kim, Jung Bok

    1999-12-01

    Providing technical support to the maintenance and repair problems of electronic instruments, we have assisted the research and development work, and reduced operation cost of the pilot plants in KAERI. In addition, we have improved the performance of the data processing system of RMS, and also modified the cyclic box using PLC which is a facility for airborne monitoring in radiation area. (author)

  10. Development of Nuclear R and D Man-power Genealogy DB and preparation of Guiding Principle in Assets Application for Nuclear R and D Fund

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Uk; Song, Seung Hyun; Kim, Hak Jun; Chung, Chul Eun

    2007-08-15

    Information search for nuclear professional man-power, technology genealogy search, project participation history etc. is serviced, and present limits to KAERI additionally, but constructed Site-Based DB that service is embodied as well as subject responsible person's pedigree. Information of professional man-power include origin school, last degree, distinction of sex, age etc. and technology genealogy consist of NuTRM classification, national science technology classification, and technology tree system classified in KAERI. Technology possession present condition for professional man-power of only KAERI is included within DB. Hereafter, professional manpower of the other nuclear energy company should be strengthened on the basis of DB structure that is developed. Technology tree system classified in KAERI also required to be strengthened on the man-power DB that has effectiveness for long-term as that embody by technology tree system which can represent nuclear energy through the verification of the other nuclear energy company. By applying readying guiding principle in assets application for nuclear R and D fund, secure lucency of assets application.

  11. Technical trend of alpha-bearing waste incinerator and R and D program in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jeong Guk; Yang, Hee Chul; Kim, Joon Hyung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    An alpha-bearing waste incineration technology is being developed from this year, after licensing the {beta}/{gamma}-bearing waste incinerator as a treatment facility for burnable wastes generated from KAERI. Some foreign incineration technologies were reviewed. The alpha-bearing waste generation in Korea and their characteristics were also discussed. 15 refs., 3 tabs., 1 fig.

  12. Establishment of Korea-Russia bilateral research collaboration for studies on biological effects of cosmic ray and space radiation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Juwoon; Kim, Dongho; Choi, Jongil; Song, Beomseok; Kim, Jaekyung; Kang, Oilhyun; Lee, Yoonjong; Kim, Jinhong; Jo, Minho

    2011-04-15

    {Omicron} KAERI-IBMP joint workshop on countermeasure and application researches to space environments - Sharing of state-of-the-art researches on space radiobiology using bio-satellites (BION-M1, Photon-soil) and ISS module (Bio-risk) was conducted - Sharing and discussion of state-of-the-art researches on dosimetry of space radiation and its affect on organisms were conducted. {Omicron} Making a contract on KAERI-IBMP Joint Research using Bio-risk module - Contract on KAERI-IBMP Joint Research to evaluate effect of space environment (microgravity and space radiation) on fermentative fungi (Aspergillus oryzae), Algae (Nostoc sp.), and plant seeds (rice, Arabidopsis thaliana, Brachypodium distachyon) was made in November, 2010. {Omicron} Discussion on new Joint Researches on evaluation of space radiation on organisms - Final step on Bion-M projects in terms of evaluation of physiological changes of lactic acid bacteria consumed by Mouse - Discussing new joint research on evaluation of physiological changes of primate by space radiation {Omicron} Establishment and management of the practical working group to invite a branch office of the IBMP in Korea - The system and the working group to implement cooperating researches between KAERI-IBMP on space radiation were established.

  13. 78 FR 72072 - Proposed Subsequent Arrangement

    Science.gov (United States)

    2013-12-02

    ... at and was prepared by KAERI, will be used for the irradiation test of full-size fuel plates in the... Concerning Civil Uses of Atomic Energy and the Agreement for Cooperation in the Peaceful Uses of Nuclear.... Sean Oehlbert, Office of Nonproliferation and International Security, National Nuclear...

  14. Calculating Program for Decommissioning Work Productivity based on Decommissioning Activity Experience Data

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Seung-Kook; Park, Hee-Seong; Moon, Jei-kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist.

  15. Maintenance and fabrication of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kwang Soo; Jeong, Jong Eun; Park, Kwang Hyeon; Hong, Suk Bong; Moon, Je Sun; Choi, Myeong Jin; Kim, Seung Bok; Kim, Jeong Bok [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    Solving the maintenance and repair problems of electronic instruments, we have supported the research and development work, and reduced operation costs of the pilot plants in KAERI. In addition, we have imposed the maintainability of instruments to use effectively. 15 tabs., 14 figs., 14 refs. (Author) .new.

  16. Design report: An off gas trapping system for a voloxidizer in INL of US

    Energy Technology Data Exchange (ETDEWEB)

    Jung, I. H.; Shin, J. M.; Park, J. J.; Park, G. I.; Lee, H. H

    2006-09-15

    This reports on the 'Development of Voloxidation Process for Treatment of LWR Spent Fuel', and it is the second year since it has started from June 2004 as a tripartite cooperation project among KAERI(Korea Atomic Energy Research Institute), INL(Idaho National Laboratory) and ORNL(Oak Ridge National Laboratory). This report is described mainly for the Task B2 accomplished during the second project year. The Task B2 in proposal contains two sub-tasks. The first one is design of an off-gas treatment system for a voloxidizer to be used in HFEF of INL. For this, KAERI team developed the design of INL OTS (Off-gas Treatment System) for hot experiment in the HFEF. INL team modified and completed the design of the INL OTS. The second task is manufacturing and test operation of the INL OTS for a voloxidizer in the INL. Manufacturing of the OTS is accomplished by INL team with co-work of KAERI. KAERI provided four sets of trapping filters needed for conducting hot experiment in the INL HFEF.

  17. Establishment of Research Infrastructure for National Advanced Radiation Technology

    Energy Technology Data Exchange (ETDEWEB)

    Kuk, Il Hiun; Byun, Myung Woo; Jeong, Il Yun; and others

    2007-07-15

    Construction of fundamental analysis system for RT/RFT advancement and pilot scale laboratory/facility for industry support and Assembly/installation of 30 MeV cyclotron for RI production and research utilizing positron beam, and construction of /distribution system for industrial and medical purpose were carried out for fast settlement for research environment of ARTI (a Jeongeup branch of KAERI)

  18. Halpha and [S II] emission from warm ionized gas in the Scutum-Centaurus Arm

    CERN Document Server

    Hill, Alex S; Haffner, L Matthew; Gostisha, Martin; Barger, Kathleen A

    2014-01-01

    We present Wisconsin H-Alpha Mapper [S II] {\\lambda}6716 and H{\\alpha} spectroscopic maps of the warm ionized medium (WIM) in the Scutum-Centaurus Arm at Galactic longitudes 310{\\deg} = 100 R. The line ratio is better correlated with H{\\alpha} intensity than with height above the plane, indicating that the physical conditions within the WIM vary systematically with electron density. We argue that the variation of the line ratio with height is a consequence of the decrease of electron density with height. Our results reinforce the well-established picture in which the diffuse H{\\alpha} emission is due primarily to emission from in situ photoionized gas, with scattered light only a minor contributor.

  19. Teaching Writing Skills in the Undergraduate Laboratory

    Science.gov (United States)

    Ugolini, Dennis W.

    1998-04-01

    Stanford University's Writing in the Major program (WIM) requires every undergraduate degree program to include a writing course specific to its field of study. In the physics department's WIM course, undergraduates learn writing skills by composing laboratory reports in the form of journal articles. While studying such topics as scintillation and population inversion, students also practice techniques for communicating the physics more effectively. Students learn how to select a thesis, organize a complex argument, write concisely, aim their content at the proper audience, prove their assertions, and revise a finished draft. Through clearer writing, students reach a clearer understanding of the physics, and the improvements in both understanding and communication stay with the students through later courses and into their graduate studies. Teaching assistants for the course also notice a marked improvement in their own writing skills.

  20. Book Reviews

    OpenAIRE

    Redactie KITLV

    2008-01-01

    Michael Williams; Deforesting the earth; From prehistory to global crisis (Greg Bankoff) Alexander Adelaar, Nikolaus P. Himmelmann (eds); The Austronesian languages of Asia and Madagascar (René van den Berg) Wim Ravesteijn, Jan Kop (eds); Bouwen in de archipel; Burgerlijke Openbare Werken in Nederlands-Indië en Indonesië 1800-2000 (Freek Colombijn) Susan Rodgers; Print, poetics, and politics; A Sumatran epic in the colonial Indies and New Order Indonesia (Bern...

  1. Uus poliitiline kriitika Ameerika filmis / Mathura

    Index Scriptorium Estoniae

    Mathura, pseud., 1973-

    2006-01-01

    Uued USA mängufilmid, mis on kriitilised oma riigi agressiivse poliitika suhtes : "Süriaana" ("Syriana") : režissöör Stephen Gaghan, "München" ("Munich") : režissöör Steven Spielberg, "Kahuriliha" ("Jarhead") : režissöör Sam Mendes, "Küllusemaa" ("Land of Plenty") : režissöör Wim Wenders

  2. Study for 228Th reduction in thermal reactor with Th-U fuel cycls

    Institute of Scientific and Technical Information of China (English)

    1999-01-01

    By using computercode WIMS/CENDL, the effects of some parameters, core configuration such as fuel element structure, neutron flux and burn-up, are discussed in thispaper.It is shown that high neutron flux, small fuel rod diameter,large volume ratio of coolant to fuel, seed-blank heterogeneous corearrangement and 231Pa chemical separation are necessary for reducing 228Th production in reactor.

  3. Computer-Based Teleconferencing and Its Impact on Command and Staff Relationships within the United States Army

    Science.gov (United States)

    1989-06-01

    decision making process. 31 IV. LABOR vs. WORK Frederick Herzberg claims that, "people labor to avoid the growing pains of depravation, while they work...collar’ versus "white collar" personnel still apply for measures of efficiency and 1.3 Frederick Herzberg . "Maximizing Work & Minimizing Labor" Industry...PROCESS (Prentice-Hall Inc. Englewood Cliffs, New Jersey. 1982). Herzberg , Frederick . "Maximizing Work and Minimizing Labor i.VYfTRY WIM", 13 October

  4. Future Developments in Non-Repudiation in GSM WAP Applications

    Directory of Open Access Journals (Sweden)

    Cristian Toma

    2009-06-01

    Full Text Available The paper presents issues and architectures for mobile applications and GSM infrastructure. The paper shows the redesign of the solution for avoiding denial of service from WAP applications using WIM features. The first section contains the structure of GSM network from voice and data point of view. The security in GSM network is presented in second chapter. The third chapter presents a solution for realizing mobile subscriber non-repudiation. The solution is based on the HTTP protocol over WAP.

  5. Accelerating Into the Future: From 0 to GeV in a Few Centimeters (LBNL Summer Lecture Series)

    Energy Technology Data Exchange (ETDEWEB)

    Leemans, Wim [LOASIS Program, AFRD

    2008-07-08

    Summer Lecture Series 2008: By exciting electric fields in plasma-based waveguides, lasers accelerate electrons in a fraction of the distance conventional accelerators require. The Accelerator and Fusion Research Division's LOASIS program, headed by Wim Leemans, has used 40-trillion-watt laser pulses to deliver billion-electron-volt (1 GeV) electron beams within centimeters. Leemans looks ahead to BELLA, 10-GeV accelerating modules that could power a future linear collider.

  6. Pertempuran Ideologi Desainer Grafis Modernisme dan Postmodernisme dalam Konteks Font Helvetica

    Directory of Open Access Journals (Sweden)

    Irwan Harnoko

    2013-03-01

    Full Text Available This article discusses the mindset of modernism designers: Massimo Vignelli, Wim Crouwel as opposed to the perspective of postmodernism designers: Paula Scher and David Carson on Helvetica font. This discussion becomes interesting because the leaders of the two sides are the key figures in the world of graphic design. Their opinions on Helvetica font can be used as a guide to study worlds graphic design, due to they dominate the mindset of contemporary designers.

  7. Assessment of CANDU reactor physics effects using a simplified whole-core MCNP model

    Energy Technology Data Exchange (ETDEWEB)

    Kozier, K.S

    2002-07-01

    A whole-core Monte Carlo n-particle (MCNP) model of a simplified CANDU reactor was developed and used to study core configurations and reactor physics phenomena of interest in CANDU safety analysis. The resulting reactivity data were compared with values derived from corresponding WIMS-AECL/RFSP, two-neutron-energy-group diffusion theory core simulations, thereby extending the range of CANDU-related code-to-code benchmark comparisons to include whole-core representations. These comparisons show a systematic discrepancy of about 6 mk between the respective absolute k{sub eff} values, but very good agreement to within about -0.15 {+-} 0.06 mk for the reactivity perturbation induced by G-core checkerboard coolant voiding. These findings are generally consistent with the results of much simpler uniform-lattice comparisons involving only WIMS-AECL and MCNP. In addition, MCNP fission-energy tallies were used to evaluate other core-wide properties, such as fuel bundle and total-channel power distributions, as well as intra-bundle details, such as outer-fuel-ring relative power densities and outer-ring fuel element azimuthal power variations, which cannot be determined directly from WIMS-AECL/RFSP core calculations. The average MCNP values for the ratio of outer fuel element to average fuel element power density agreed well with corresponding values derived from WIMS-AECL lattice-cell cases, showing a small systematic discrepancy of about 0.5 %, independent of fuel bum-up. For fuel bundles containing the highest-power fuel elements, the maximum peak-to-average outer-element azimuthal power variation was about 2.5% for cases where a statistically significant trend was observed, while much larger peak-to-average outer-element azimuthal power variations of up to around 42% were observed in low-power fuel bundles at the core/radial-neutron-reflector interface. (author)

  8. Three Dimensionally Interconnected Silicon Nanomembranes for Optical Phased Array (OPA) and Optical True Time Delay (TTD) Applications

    Science.gov (United States)

    2012-06-01

    splitter design techniques for on- chip optical interconnections,” IEEE Jounal of Selected Topics in Quantum Electronics 17, 510-515 (2011). [3-8] P...Electro-Optics/ Quantum Electronics and Laser Science Conference and Photonic 25 | P a g e Applications Systems Technologies, OSA Technical Digest...Silicon-on-Insulator Substrate," Jpn. J. Appl. Phys. 50 (2011) 120208. [3-19] Shankar Kumar Selvaraja, WimBogaerts, Dries VanThourhout, and Marc

  9. Europeaisches Kern Forschungszentrum

    CERN Multimedia

    US Information Service in Germany

    1959-01-01

    Propaganda film (heroic) which emphasises international collaboration. No practical application of the work which goes on here. Interesting facts which come up: CERN employed 1000 people, average age of 33 years. Ford Foundation paid many people. Just after PS comes into operation, no talk of experiments. Very little explanation of what goes on at CERN. Images of: CERN cafetaria, CERN main building, CERN personalities (Lew Kowarski, Wim Klein, Roger Anthoine ....)

  10. Reference: 551 [Arabidopsis Phenome Database[Archive

    Lifescience Database Archive (English)

    Full Text Available 551 http://metadb.riken.jp/db/SciNetS_ria224i/cria224u4ria224u17329563i Liu Yongxiu et al. 2007 Fe...in the Arabidopsis hub1 (rdo4) mutant reveals a role for chromatin remodeling in seed dormancy. 2 433-44 17329563 2007 Feb The Plant cell Koornneef Maarten|Liu Yongxiu|Soppe Wim J J

  11. System and method for identifying, validating, weighing and characterizing moving or stationary vehicles and cargo

    Science.gov (United States)

    Beshears, David L.; Batsell, Stephen G.; Abercrombie, Robert K.; Scudiere, Matthew B.; White, Clifford P.

    2007-12-04

    An asset identification and information infrastructure management (AI3M) device having an automated identification technology system (AIT), a Transportation Coordinators' Automated Information for Movements System II (TC-AIMS II), a weigh-in-motion system (WIM-II), and an Automated Air Load Planning system (AALPS) all in electronic communication for measuring and calculating actual asset characteristics, either statically or in-motion, and further calculating an actual load plan.

  12. Determination of Practical ESALs Per Truck Values on Indiana Roads

    OpenAIRE

    2000-01-01

    The Indiana Department of Transportation (INDOT) has been using ESAL (Equivalent Single Axle Load) values for pavement design. The current ESAL values were obtained in the late 1970. However, truck deregulation and higher allowable maximum loads have increased the 1970's values. Updated ESAL values are needed for better road designs. The 1998 and 1999 traffic data from the all Weight-in-Motion (WIM) stations were obtained and used to compute updated ESAL values for multiple unit trucks (Class...

  13. Formation and evolution of magma-poor margins, an example of the West Iberia margin

    Science.gov (United States)

    Perez-Gussinye, Marta; Andres-Martinez, Miguel; Morgan, Jason P.; Ranero, Cesar R.; Reston, Tim

    2016-04-01

    The West Iberia-Newfoundland (WIM-NF) conjugate margins have been geophysically and geologically surveyed for the last 30 years and have arguably become a paradigm for magma-poor extensional margins. Here we present a coherent picture of the WIM-NF rift to drift evolution that emerges from these observations and numerical modeling, and point out important differences that may exist with other magma-poor margins world-wide. The WIM-NF is characterized by a continental crust that thins asymmetrically and a wide and symmetric continent-ocean transition (COT) interpreted to consist of exhumed and serpentinised mantle with magmatic products increasing oceanward. The architectural evolution of these margins is mainly dominated by cooling under very slow extension velocities (crust that most probably was not extremely weak at the start of rifting. These conditions lead to a system where initially deformation is distributed over a broad area and the upper, lower crust and lithosphere are decoupled. As extension progresses upper, lower, crust and mantle become tightly coupled and deformation localizes due to strengthening and cooling during rifting. Coupling leads to asymmetric asthenospheric uplift and weakening of the hanginwall of the active fault, where a new fault forms. This continued process leads to the formation of an array of sequential faults that dip and become younger oceanward. Here we show that these processes acting in concert: 1) reproduce the margin asymmetry observed at the WIM-NF, 2) explain the fault geometry evolution from planar, to listric to detachment like by having one common Andersonian framework, 3) lead to the symmetric exhumation of mantle with little magmatism, and 4) explain the younging of the syn-rift towards the basin centre and imply that unconformities separating syn- and post-rift may be diachronous and younger towards the ocean. Finally, we show that different lower crustal rheologies lead to different patterns of extension and to an

  14. Russki "Tjulpan" pokoril lazurnõi bereg / Maria Davtjan, Tatjana Pinskaja

    Index Scriptorium Estoniae

    Davtjan, Maria

    2008-01-01

    61. Cannes'i filmifestival on lõppenud. Vaatenurga preemia sai Kasahstani režissöör Sergei Dvortsevoi filmi "Tulp" ("Tjulpan") eest. Lisatud ka lühiintervjuu režissööriga. Ka mõnest filmist, nii auhinnatuist (Steven Soderbergh'i "Che", Clint Eastwoodi "Changeling") kui ilmajäänuist (Atom Egoyani "Adoration", Wim Wendersi "Palermo Shooting"), Sharon Stone'i juhitud heategevast AIDSi ravi toetavast oksjonist

  15. TRIGA MARK-II source term

    Energy Technology Data Exchange (ETDEWEB)

    Usang, M. D., E-mail: mark-dennis@nuclearmalaysia.gov.my; Hamzah, N. S., E-mail: mark-dennis@nuclearmalaysia.gov.my; Abi, M. J. B., E-mail: mark-dennis@nuclearmalaysia.gov.my; Rawi, M. Z. M. Rawi, E-mail: mark-dennis@nuclearmalaysia.gov.my; Abu, M. P., E-mail: mark-dennis@nuclearmalaysia.gov.my [Bahagian Teknologi Reaktor, Agensi Nuklear Malaysia, 43000 Kajang (Malaysia)

    2014-02-12

    ORIGEN 2.2 are employed to obtain data regarding γ source term and the radio-activity of irradiated TRIGA fuel. The fuel composition are specified in grams for use as input data. Three types of fuel are irradiated in the reactor, each differs from the other in terms of the amount of Uranium compared to the total weight. Each fuel are irradiated for 365 days with 50 days time step. We obtain results on the total radioactivity of the fuel, the composition of activated materials, composition of fission products and the photon spectrum of the burned fuel. We investigate the differences of results using BWR and PWR library for ORIGEN. Finally, we compare the composition of major nuclides after 1 year irradiation of both ORIGEN library with results from WIMS. We found only minor disagreements between the yields of PWR and BWR libraries. In comparison with WIMS, the errors are a little bit more pronounced. To overcome this errors, the irradiation power used in ORIGEN could be increased a little, so that the differences in the yield of ORIGEN and WIMS could be reduced. A more permanent solution is to use a different code altogether to simulate burnup such as DRAGON and ORIGEN-S. The result of this study are essential for the design of radiation shielding from the fuel.

  16. Extended nebular emission in CALIFA early-type galaxies

    CERN Document Server

    Gomes, J M; Kehrig, C; Vílchez, J M; Lehnert, M D

    2015-01-01

    The morphological, spectroscopic and kinematical properties of the warm interstellar medium (wim) in early-type galaxies (ETGs) hold key observational constraints to nuclear activity and the buildup history of these massive quiescent systems. High-quality integral field spectroscopy (IFS) data with a wide spectral and spatial coverage, such as those from the CALIFA survey, offer a precious opportunity for advancing our understanding in this respect. We use deep IFS data from CALIFA (califa.caha.es) to study the wim over the entire extent and optical spectral range of 32 nearby ETGs. We find that all ETGs in our sample show faint (H\\alpha\\ equivalent width EW~0.5...2 {\\AA}) extranuclear nebular emission extending out to >= 2 Petrosian_50 radii. Confirming and strengthening our conclusions in Papaderos et al. (2013) we argue that ETGs span a broad continuous sequence with regard to the properties of their wim, and they can be roughly subdivided into two characteristic classes. The first one (type i) comprises E...

  17. The warm ionized gas in CALIFA early-type galaxies: 2D emission-line patterns and kinematics for 32 galaxies

    CERN Document Server

    Gomes, J M; Kehrig, C; Vílchez, J M; Lehnert, M D; Sánchez, S F; Ziegler, B; Breda, I; Reis, S N dos; Iglesias-Páramo, J; Bland-Hawthorn, J; Galbany, L; Bomans, D J; Rosales-Ortega, F F; Fernandes, R Cid; Walcher, C J; Falcón-Barroso, J; García-Benito, R; Márquez, I; del Olmo, A; Masegosa, J; Mollá, M; Marino, R A; Delgado, R M González; López-Sánchez, Á R

    2015-01-01

    The morphological, spectroscopic and kinematical properties of the warm interstellar medium (wim) in early-type galaxies (ETGs) hold key observational constraints to nuclear activity and the buildup history of these massive, quiescent systems. High-quality integral field spectroscopy (IFS) data with a wide spectral and spatial coverage, such as those from the CALIFA survey, offer an unprecedented opportunity for advancing our understanding of the wim in ETGs. This article centers on a 2D investigation of the wim component in 32 nearby (<~150Mpc) ETGs from CALIFA, complementing a previous 1D analysis of the same sample (Papaderos et al. 2013; P13). We include here H\\alpha\\ intensity and equivalent width (EW) maps and radial profiles, diagnostic emission-line ratios, besides ionized-gas and stellar kinematics. This study is supplemented by \\tau-ratio maps as an efficient means to quantify the role of photoionization by pAGB stars, as compared to other mechanisms (e.g., AGN, low-level star formation). Additio...

  18. TRIGA MARK-II source term

    Science.gov (United States)

    Usang, M. D.; Hamzah, N. S.; J. B., Abi M.; M. Z., M. Rawi; Abu, M. P.

    2014-02-01

    ORIGEN 2.2 are employed to obtain data regarding γ source term and the radio-activity of irradiated TRIGA fuel. The fuel composition are specified in grams for use as input data. Three types of fuel are irradiated in the reactor, each differs from the other in terms of the amount of Uranium compared to the total weight. Each fuel are irradiated for 365 days with 50 days time step. We obtain results on the total radioactivity of the fuel, the composition of activated materials, composition of fission products and the photon spectrum of the burned fuel. We investigate the differences of results using BWR and PWR library for ORIGEN. Finally, we compare the composition of major nuclides after 1 year irradiation of both ORIGEN library with results from WIMS. We found only minor disagreements between the yields of PWR and BWR libraries. In comparison with WIMS, the errors are a little bit more pronounced. To overcome this errors, the irradiation power used in ORIGEN could be increased a little, so that the differences in the yield of ORIGEN and WIMS could be reduced. A more permanent solution is to use a different code altogether to simulate burnup such as DRAGON and ORIGEN-S. The result of this study are essential for the design of radiation shielding from the fuel.

  19. Effectiveness of vehicle weight enforcement in a developing country using weigh-in-motion sorting system considering vehicle by-pass and enforcement capability

    Directory of Open Access Journals (Sweden)

    Mohamed Rehan Karim

    2014-03-01

    Full Text Available Vehicle overloading has been identified as one of the major contributors to road pavement damage in Malaysia. In this study, the weigh-in-motion (WIM system has been used to function as a vehicle weight sorting tool to complement the exsiting static weigh bridge enforcement station. Data collected from the developed system is used to explore the effectiveness of using WIM system in terms of generating more accurate data for enforcement purposes and at the same time improving safety and reducing the number of vehicle weight violations on the roads. This study specifically focus on the effect of vehicle by-pass and static weigh station enforcement capability on the overall effectiveness of vehicle weight enforcement system in a developing country. Results from this study suggest that the WIM system will significantly enhance the effectiveness and efficiency of the current vehicle weight enforcement, thus generating substantial revenue that would greatly off-set the current road maintenance budget that comes from tax payers money. If there is substantial reduction in overloaded vehicles, the public will still gain through reduction in road maintenance budget, less accident risks involving heavy trucks, and lesser greenhouse gases (GHGs emissions.

  20. AN overview of the FLYSAFE datalink solution for the exchange of weather information: supporting aircrew decision making processes.

    Science.gov (United States)

    Mirza, A.; Drouin, A.

    2009-09-01

    FLYSAFE is an Integrated Project of the 6th framework of the European Commission with the aim to improve flight safety through the development of an avionics solution the Next Generation Integrated Surveillance System (NGISS), which is supported by a ground based network of Weather Information Management Systems (WIMS) and access points in the form of the Ground Weather Processor (GWP). The NGISS provides information to the flight crew on the three major external hazards for aviation: weather, air traffic and terrain. The NGISS has the capability of displaying data about all three hazards on a single display screen, facilitating rapid appreciation of the situation by the flight crew. Weather Information Management Systems (WIMS) were developed to provide the NGISS and the flight crew with weather related information on in-flight icing, thunderstorms and clear-air turbulence. These products are generated on the ground from observations and model forecasts. WIMS will supply relevant information on three different scales: global, regional and local (over airport Terminal Manoeuvring Area). The Ground Weather Processor is a client-server architecture that utilises open source components, which include a geospatial database and web feature services. The GWP stores Weather Objects generated by the WIMS. An aviation user can retrieve on-demand all Weather Objects that intersect the volume of space that is of interest to them. The Weather Objects are fused with in-situ observation data and can be used by the flight management system to propose a route to avoid the hazard. In addition they can be used to display the current hazardous weather to the Flight Crew thereby raising their awareness. Within the FLYSAFE program, around 120 hours of flight trials were performed during February 2008 and August 2008. Two aircraft were involved each with separate objectives: - to assess FLYSAFE's innovative solutions for the data-link, on-board data-fusion and data-display and data

  1. Biological efficiency of interaction between various radiation and chemicals

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jin Kyu; Yu, Dong Han; Lee, Byoung Hun [KAERI, Taejon (Korea, Republic of); Petin, Vladislav G. [Medical Radiology Science Center, Obninsk (Russian Federation); Geras' kin, Stanislav A. [Russian Institute of Agricultural Radiology and Ecology, Obninsk (Russian Federation); Cebulska-Wasilewska, Antonina; Panek, Agnieszka; Wiechec, Anna [Institute of Nuclear Physics, Cracow (Poland)

    2004-06-01

    This research project has been carried out jointly with INP (Poland) to develop technologies to assess the biological efficiency of interaction between radiation and chemicals. Through the cooperative project, KAERI and INP have established wide variety of bioassay techniques applicable to radiation bioscience, human monitoring, molecular epidemiology and environmental science. The joint experiment, in special, made it possible to utilize the merits of both institutes and to upgrade and verify KAERI's current technology level. All results of the cooperative research will be jointly published in high standard scientific journals listed in the Science Citation Index (SCI), which can make the role of fundamental basis for improving relationship between Korea and Poland. Research skills such as Trad-MCN assay, SCGE assay, immunohistochemical assay and molecular assay developed through joint research will be further elaborated and will be continuously used for the collaboration between two institutes.

  2. Large break loss-of-coolant accident analysis for China Qinshan-2 nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Yong; Ban, Chang Hwan; Chung, Bub Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Wang, Rongzhong; Yu, Hongxing [Nuclear Power Institute of China, Chengdu, SC (China)

    1994-12-01

    Large break LOCA analysis for China Qinshan-2 nuclear power plant has been performed using realistic evaluation model which has been being developed by KAERI. RELAP5/MOD3/KAERI code, which is a modified version of RELAP5/MOD3, is coupled with CONTEMPT4/MOD5 and is used as a best estimate code to predict the thermal hydraulic behavior of the system. PCT uncertainty which stems from code uncertainty, plant application uncertainty, scaling uncertainty and PCT bias are discussed. Among them, plant application uncertainty is described in detail. The licensing PCT is calculated by adding all the uncertainties to the best-estimate PCT. The result indicates the Qinshan-2 nuclear power plant has at least 37 deg C safety margin for large break LOCA. (Author) 10 refs., 47 figs., 14 tabs.

  3. Development of a preliminary PIRT (Phenomena Identification and Ranking Table) of thermal-hydraulic phenomena for 330MWt SMART integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, B. D.; Lee, W. J.; Sim, S. K.; Song, J. H.; Kim, H. C.

    1997-09-01

    The work reported in this document identifies the thermal-hydraulic phenomena that are expected to occur during a number of key transients in a 330 MWt SMART integral reactor which is under development at KAERI. The result of this efforts is based on the current design concept of SMART integral reactor. Although the design is still evolving, the preliminary Phenomena Identification and Ranking Table (PIRT) has been developed based on the experts` knowledge and experience. The preliminary PIRT has been developed by the consensus of KAERI expert panelists and AHP (Analytical Hierarchy Process). Preliminary PIRT developed in this report is intended for use to identify and integrate development areas of further experimental tests needed and thermal-hydraulic models and correlations and code improvements for the safety analysis of the SMART integral reactor. (author). 7 refs., 21 tabs., 22 figs.

  4. Development of a preliminary PIRT (Phenomena Identification and Ranking Table) of thermal-hydraulic phenomena for SMART

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Bub Dong; Lee, Won Jae; Kim, Hee Cheol; Song, Jin Ho; Sim, Suk Ku [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The work reported in this paper identifies the thermal-hydraulic phenomena that are expected to occur during a number of key transients in SMART (System-integrated Modular Advanced ReacTor) which is under development at KAERI. The result of this effort is based on the current design concept of SMART integral reactor. Although the design is still evolving, the preliminary Phenomena Identification and Ranking Table (PIRT) has been developed based on the experts` knowledge and experience. The preliminary PIRT has been developed by consensus of KAERI expert panelists and AHP (Analytical Hierarchy Process). Preliminary PIRT developed in this paper is intended to be used to identify and integrate development areas of further experimental tests needed, thermal hydraulic models and correlations and code improvements for the safety analysis of the SMART. 8 refs., 4 tabs (Author)

  5. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho

    2000-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author)

  6. Development of the Decommissioning Project Management System, DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Park, J. H.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-03-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The management of the projects can be defined as 'the decision of the changes of the decommissioning methodologies for the more efficient achievement of the project at an adequate time and to an improved method'. The correct decision comes from the experiences on the decommissioning project and the systematic experiences can be obtained from the good management of the decommissioning information. For this, a project management tool, DECOMMIS, was developed in the D and D Technology Division, which has the charge of the decommissioning projects at the KAERI, and its purpose was extended to following fields; generation of reports on the dismantling waste for WACID, record keeping for the next decommissioning projects of nuclear facilities, provision of fundamental data for the R and D of the decommissioning technologies.

  7. Technical cooperation for the wider uses of Ho-166 therapeutic agents in European countries

    CERN Document Server

    Park, K B; Choi, S M; Han, K H; Hong, Y D; Park, W W; Shin, B C

    2002-01-01

    Czech has put their priority in developing the radiopharmaceuticals based on reactor produced Ho-166 and a related fabrication will be extended to other EU conturies including Germany, France, etc after a development of project. The collaboration will be based on the mutual agreement for developing the between research institutes, industries and academic institutes and further researches should be followed by the issue of developing radiopharmaceuticals using Ho-166. To strengthen the collaboration, detailed discussions for the practical collaboration have been made through the visitation to the research institution of each counter part. For implementing the collaboration between NPI and KAERI, an institutional basis technical cooperation agreement(TCA) will be concluded. Furthermore, agreement for the substantial collaboration on Ho-166 related researches will be made after the conclusion of the TCA. It will accelerate the commercialization of KAERI developed Ho-166 therapeutic agents into other European cou...

  8. The Hydraulic Test Procedure for Non-instrumented Irradiation Test Rig of Annular Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dae Ho; Lee, Kang Hee; Shin, Chang Hwan; Park, Chan Kook

    2008-08-15

    This report presents the procedure of pressure drop test, vibration test and endurance test for the non-instrumented rig using the irradiation test in HANARO of advanced PWR annular fuel which were designed and fabricated by KAERI. From the out-pile thermal hydraulic tests, confirm the flow rate at the 200 kPa pressure drop and measure the RMS displacement at this time. And the endurance test is confirmed the wear and the integrity of the non-instrumented rig at the 110% design flow rate. This out-pile test perform the Flow-Induced Vibration and Pressure Drop Experimental Tester(FIVPET) facility. The instruments in FIVPET facility was calibrated in KAERI and the pump and the thermocouple were certified by manufacturer.

  9. A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

    Energy Technology Data Exchange (ETDEWEB)

    Rho, Si Pyo; Kim, Cheol Jung; Yoo, Bung Duk; Kim, Jae Woo; Lee, Myung Ho; Kim, Kyung Pyo

    2006-02-15

    The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia.

  10. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho; Lee, M.H. [and others

    1999-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author). 3 refs., 50 tabs., 12 figs.

  11. Basic requirements for a preliminary conceptual design of the Korea advanced pyroprocess facility (KAPF)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ho Hee; Ko, Won Il; Chang, Hong Lae; Song, Dae Yong; Kwon, Eun Ha; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-12-15

    Korea Atomic Energy Research Institute (KAERI) has been developing technologies for pyroprocessing for spent PWR fuels. This study is part of a long term R and D program in Korea to develop an advanced recycle system that has the potential to meet and exceed the proliferation resistance, waste minimization, resource minimization, safety and economic goals of approved Korean Government energy policy, as well as the Generation IV International Forum (GIF) program. To support this R and D program, KAERI requires that an independent estimate be made of the conceptual design and cost for construction and operation of a 'Korea Advanced Pyroprocessing Facility', This document describes the basic requirements for preliminary conceptual design of the Korea Advanced Pyroprocess Facility (KAPF). The presented requirements will be modified to be more effective and feasible on an engineering basis during the subsequent design process.

  12. MELCOR DB Construction for the Severe Accident Analysis DB

    Energy Technology Data Exchange (ETDEWEB)

    Song, Y. M.; Ahn, K. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-10-15

    The Korea Atomic Energy Research Institute (KAERI) has been constructing a severe accident analysis database (DB) under a National Nuclear R and D Program. In particular, an MAAP (commercial code being widely used in industries for integrated severe accident analysis) DB for many scenarios including a station blackout (SBO) has been completed. This paper shows the MELCOR DB construction process with examples of SBO scenarios, and the results will be used for a comparison with the MAAP DB

  13. The management of radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Jeong; An, Sum Jin; Lee, Kang Moo; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Sohn, Young Jun; Yim, Kil Sung; Kim, Tae Kuk; Jeong, Kyeong Hwan; Wi, Keum San; Park, Young Yoong; Park, Seung Chul; Lee, Chul Yong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    The radioactive wastes generated at Korea Atomic Energy Research Institute (KAERI) in 1994 are about 56 m{sup 3} of liquid waste and 323 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. The solid wastes were treated in 1994 are about 87 m{sup 3} of liquid waste and 81 drums of solid waste, respectively. 2 tabs., 26 figs., 12 refs. (Author) .new.

  14. Seismic Fragility Analysis of a Condensate Storage Tank with Age-Related Degradations

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Braverman, J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Hofmayer, C [Brookhaven National Lab. (BNL), Upton, NY (United States); Choun, Y-S [Brookhaven National Lab. (BNL), Upton, NY (United States); Kim, MK [Brookhaven National Lab. (BNL), Upton, NY (United States); Choi, I-K [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2011-04-01

    The Korea Atomic Energy Research Institute (KAERI) is conducting a five-year research project to develop a realistic seismic risk evaluation system which includes the consideration of aging of structures and components in nuclear power plants (NPPs). The KAERI research project includes three specific areas that are essential to seismic probabilistic risk assessment (PRA): (1) probabilistic seismic hazard analysis, (2) seismic fragility analysis including the effects of aging, and (3) a plant seismic risk analysis. Since 2007, Brookhaven National Laboratory (BNL) has entered into a collaboration agreement with KAERI to support its development of seismic capability evaluation technology for degraded structures and components. The collaborative research effort is intended to continue over a five year period. The goal of this collaboration endeavor is to assist KAERI to develop seismic fragility analysis methods that consider the potential effects of age-related degradation of structures, systems, and components (SSCs). The research results of this multi-year collaboration will be utilized as input to seismic PRAs. This report describes the research effort performed by BNL for the Year 4 scope of work. This report was developed as an update to the Year 3 report by incorporating a major supplement to the Year 3 fragility analysis. In the Year 4 research scope, an additional study was carried out to consider an additional degradation scenario, in which the three basic degradation scenarios, i.e., degraded tank shell, degraded anchor bolts, and cracked anchorage concrete, are combined in a non-perfect correlation manner. A representative operational water level is used for this effort. Building on the same CDFM procedure implemented for the Year 3 Tasks, a simulation method was applied using optimum Latin Hypercube samples to characterize the deterioration behavior of the fragility capacity as a function of age-related degradations. The results are summarized in Section 5

  15. Characteristics and performance analysis report of the major thermal hydraulic components in the high temperature/high pressure thermal hydraulic test facility (VISTA)

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ki Yong; Park, Hyun Sik; Cho, Seok; Lee, Sung Jae; Song, Chul Hwa; Park, Chun Kyong; Chung, Moon Ki

    2003-12-01

    The VISTA (Experimental Verification by Integral Simulation of Transients and Accidents) is an experimental facility to verify the performance and safety issues of the SMART-P (Pilot plant of the System-integrated Modular Advanced Reactor). The basic design of the SMART-P has been completed by KAERI. The present report describes the characteristics and performance of the major thermal hydraulic components in the VISTA Facility.

  16. Experimental Report for Thermal Hydraulic Behavior During Startup, Power Change and MCP Transient Operation by using the High Temperature/High Pressure Test Facility(VISTA)

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ki Yong; Park, Hyun Sik; Cho, Seok; Lee, Sung Jae; Choi, Nam Hyun; Min, Kyong Ho; Song, Chul Hwa; Park, Chun Kyong; Chung, Moon Ki

    2005-07-15

    The VISTA (Experimental Verification by Integral Simulation of Transients and Accidents) is an experimental facility to verify the performance and safety issues of the SMART-P (Pilot plant of the System-integrated Modular Advanced Reactor). The basic design of the SMART-P has been completed by KAERI. The present report describes experimental test results for performance test items, including heatup, power change, MCP transient, and natural circulation operations by using the VISTA facility.

  17. Scaled-Down Moderator Circulation Test Facility at Korea Atomic Energy Research Institute

    OpenAIRE

    2016-01-01

    Korea Atomic Energy Research Institute (KAERI) started the experimental research on moderator circulation as one of a the national research and development programs from 2012. This research program includes the construction of the moderator circulation test (MCT) facility, production of the validation data for self-reliant computational fluid dynamics (CFD) tools, and development of optical measurement system using the particle image velocimetry (PIV). In the present paper we introduce the sc...

  18. Major Achievements and Prospect of the ATLAS Integral Effect Tests

    OpenAIRE

    2012-01-01

    A large-scale thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been operated by KAERI. The reference plant of ATLAS is the APR1400 (Advanced Power Reactor, 1400 MWe). Since 2007, an extensive series of experimental works were successfully carried out, including large break loss of coolant accident tests, small break loss of coolant accident tests at various break locations, steam generator tube rupture tests, feed line ...

  19. Fluid dynamics evaluation of split vane grid spacer in a small modular reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nazififard, Mohammad [Kashan Univ (Iran, Islamic Republic of). Dept. of Energy System Engineering; Seoul National Univ. (Korea, Republic of). Dept. of Nuclear Engineering; Philosophia, Seoul (Korea, Republic of); Nematollahi, Mohammadreza [Shiraz Univ. (Iran, Islamic Republic of). Dept. of Nuclear Engineering; Suh, Kune Y. [Seoul National Univ. (Korea, Republic of). Dept. of Nuclear Engineering; Philosophia, Seoul (Korea, Republic of)

    2015-12-15

    This paper numerically evaluates the effect of a split vane grid spacer on thermohydrodynamics in a subchannel of a typical small modular pressurized water reactor. The turbulent convective heat transfer and pressure drop are numerically calculated. Thermohydrodynamics and neutronics coupling would indeed be interesting for more quantitative analyses of the fuel assembly design, heat transfer correlation and mixing coefficient for the System-Integrated Modular Advanced Reactor (SMART) being developed by the Korea Atomic Energy Research Institute (KAERI).

  20. Nuclear design aspect of the Korean high intensity proton accelerator project

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Jonghwa; Song, Tae-Yung [Korea Atomic Energy Research Inst., Yusong, Taejon (Korea, Republic of)

    1998-11-01

    A plan to construct a high current proton accelerator has been proposed by KAERI. We are presenting the required nuclear design to support the project as well as a brief overview of the proposed proton accelerator. The target and core design is highlighted to show feasibility of incineration of minor actinides from the spent fuel of light water reactors. Radiation shielding and activation analyses are also important for the design and the license of the accelerator. (author)

  1. Ventilation system of actinides handling facility in Oarai-branch of Tohoku University

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Yoshimitsu; Watanabe, Makoto; Hara, Mituo; Shikama, Tatsuo; Kayano, Hideo; Mitsugashira, Toshiaki [Oarai Branch, Institute for Materials Research, Tohoku Univ., Oarai, Ibaraki (Japan)

    1999-09-01

    We have reported the development of the facility for handling actinides in Tohoku University at the second KAERI-JAERI joint seminar on PIE technology. Actinide isotopes have most hazurdous {alpha}-radioactivity. Therefore, a specially designed facility is necessary to carry out experimental study for actinide physics and chemistry. In this paper, we will describe the ventilation system and monitoring system for actinide handling facility. (author)

  2. The first technical report for the improvement of R and D evaluation : Focusing on the evaluation reaction of R and D project investigator

    Energy Technology Data Exchange (ETDEWEB)

    Yeo, Ji Won; Kim, I.C.; Won, B.C.; Kim, M.R. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1997-12-01

    The main objectives of this report are as follows. - Measuring the project manager's reaction on R and D evaluation and determining its influencing factors. - Testing the relationship between personal characteristics (tolence for ambiguity, risk-taking propensity, self-efficacy, Turn-over intention) and the outcome of Project Evaluation. - Presenting the useful information related to rebuilding a R and D Evaluation System of KAERI (Korea Atomic Energy Research Institute). 72 refs., 6 figs., 41 tabs. (Author)

  3. NUCLEAR HYDROGEN DEVERLOPMENT AND DEMONSTRATION PROGRAM IN KOREA

    Institute of Scientific and Technical Information of China (English)

    林昌奎; 朴原奭; 张锺和

    2004-01-01

    The Korea Atomic Energy Research Institute (KAERI) launched a nuclear hydrogen program to develop and demonstrate a hydrogen mass production system by 2019. The key feature of the system is to produce the hydrogen from water using nuclear power. No fossil fuel (energy) will be used and no greenhouse gas will be emitted. The high temperature gas-cooled reactor (HTGR), which has high safety characteristics with competitive economy, is being developed to provide a high temperature heat (about 1000℃) requir...

  4. Development of real-time monitoring and control in COIL laser cutting for joint R and D between Korea and U.S

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chin Man; Kim, Cheol Jung; Kim, Min Suk; Baik, Sung Hoon; Kwon, Sung Ok; Park, Sun Kyu

    2000-12-01

    The laser monitoring and control technique investigated to experiment for cutting kerf width and result of laser cutting for D and D of nuclear facility. The demands for this laser monitoring and control technique were applied to process control in laser cutting and to fabricate monitoring and control system, focusing lens assembly. This system can had a advantage to monitor and control the laser cutting on real time. KAERI investigated the COIL laser and monitored 2 kW laser power.

  5. Participation in benchmark MATIS-H of NEA/OCDE: uses CFD codes applied to nuclear safety. Study of the spacer grids in the fuel elements; Participacion en el Benchmark Matis-H de la NEA/OCDE: usos de codigos CFD aplicados a seguridad nuclear. Estudio de las rejillas espaciadoras en los elementos combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Pena-Monferrer, C.; Chiva, S.; Munoz-cobo, J. L.; Vela, E.

    2012-07-01

    This paper develops participation in benchmark MATIS-H, promoted by the NEA / OECD-KAERI, involving the study of turbulent flow in a rod beam with spacers in an experimental installation. Its aim is the analysis of hydraulic behavior of turbulent flow in the subchannels of the fuel elements, essential for the improvement of safety margins in normal and transient operations and to maximize the use of nuclear energy through an optimal design of grids.

  6. Development on the radiological emergency management guide

    Energy Technology Data Exchange (ETDEWEB)

    Khang, Byung Oui; Lee, Jong Tai; Lee, Goan Yup; Lee, Moon

    2000-01-01

    The comprehensive emergency management system in KAERI describes the requirements for emergency plan, preparedness, evaluations and readiness assurance, response and recovery activities to timely and effectively countermeasure according to the type and size of an event. The guidance of facility emergency plan and detailed response procedures for initial action, building/site evacuation, personnel accountability, search and fire fighting in the radioactive, fissionable, toxic and inflammable hazardous substances handling facilities are also developed. (author)

  7. A development of SDLC for MMIS of SMART research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Yong Suk; Park, Jae Hong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Koo, In Soo; Kim, Jong Myung; Park, Dong Cheol [Control Tech. Research Inst., Ulsan (Korea, Republic of); Kim, Hyeon Soo [Chungnam National University, Taejon (Korea, Republic of)

    2004-07-01

    Software development concept for Man Machine Interface System (MMIS) of SMART has been researched in KAERI since 2000. As a result of it, we developed Software Development Life Cycle (SDLC) based on IEEE Std 1074(1997) and submitted it to Korea Institute of Nuclear Safety (KINS) as a part of Pre-SAR. We verify that the SDLC meets IEEE Std 1074(1997) by making mapping table between them in this paper.

  8. Nuclear design manual for generation of cross section and heterogeneous formfunction for CASMO-3/MASTER

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Ho; Cho, Byung Oh; Song, Jae Seong; Lee, Chung Chan

    1996-12-01

    A three-dimensional reactor core simulation code, MASTER, has been developed as a part of the ADONIS project in KAERI. CASMO-3 prepares various two-group cross sections for the constituents of a reactor core such as fuel assembly, radial and axial reflectors, control rod and detector for MASTER. This report includes the standard design procedure for generation of two-group cross sections and heterogeneous formfunction by CASMO-3/FORM for MASTER. (author). 16 refs., 16 tabs., 12 figs.

  9. KEIMS utility manual (edition 1.0)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeun Seung; Eom, Young Sam; Choi, Jin Yeup; Nam, Ji Hwa [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    Since 1987 when KAERI had started Yonggwang 3 and 4 NSSS system design project, KAERI has carried out so many NSSS system design projects such as Ulchin 3 and 4, Wolsong 2, 3 and 4 and Yonggwang 5 and 6 with fixed members that necessity of increasing productivity has been raised. To improve design work efficiency, it was considered that computerization of workflow which took so much man-power and business time. As result of investigation of design workflow to reduce man-power loss. It was suggested that DDA (Document Distribution for Agreement) workflow, design document stored in DDCD (Document Distribution and Control Center), IOC (Interoffice Correspondence) document, Letter, PM Memo should be preferentially computerized. On the basis of these computerization requirements, MEDIS (Modular Engineering Document Imaging System) was selected. Prototype had been implemented during 1995.9 -1995.12, and from 1996.1 KEIMS (KAERI Engineering Information Management System) has been operated. This MEDIS system utility manual was composed of several technical memos which has been described on customization of MEDIS fit to KEIMS, program development for system check, and information control of database. Further edition would be released as utility technical memo added. (Author) .new.

  10. Nuclear Manpower Development

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, I. A.; Lee, K. B.; Shin, B. C. [KAERI, Daejeon (Korea, Republic of)

    2010-12-15

    The industry-university-research collaborative education is aiming at developing national nuclear human resources to satisfy with the increasing needs from the industry. For this efforts are being made to develop curricula customized to respective industry needs by improving existing ones. As the demand for training programs for the university students and domestic nuclear personnel was increasing owing to revitalization of nuclear industry, Nuclear Training Center (NTC) improved previous education programs to meet the needs. NTC has operated 2 education programs on research reactor experiments for the university students, and 18 programs on nuclear technology related experiment courses in 2010. Furthermore, the NTC developed new education programs related to 'standardized research reactor system design'. Also the request from universities for internship programs was increased by about three times in 2010 compared to those of the previous year, and this required to develop relevant curricula. In 2005, NTC developed KAERI-ACE, as a unique competency-based staff education system of Korea Atomic Energy Research Institute (KAERI). Based on the system, the NTC has performed 'systematic education'. In 2008, NTC was awarded Best HRD(Human Resource Development) in Public sector for the first time as a government-supported research institute. In 2009, the system was improved to become KAERI-ACE 2.0, based on which, in 2010, NTC improved and diversified education programs including various cyber training programs

  11. Establish the Foundation of Environmental Assessment Technique in ROK via the International Environmental Modelling for Radiation Safety Managed by IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Han Soo; Choi, Y. H.; Keum, D. K.; Kang, H. S.; Ahn, S. S.; Chung, Y. S.; Lee, C. W.; Hwang, W. T.; Seo, K. S

    2005-08-15

    Tritiated water (HTO) released from the nuclear facilities can easily be absorbed by plants via their stomata and incorporated into organics by metabolic processes such as photosynthesis. Organically bound tritium (OBT) in plant cells is mostly inexchangeable and remains at harvest to contribute some to the ingestion radiation dose (Barry et al., 1999). In assessing the ingestion dose due to an accidental release of HTO, a dynamic model simulating its environmental behaviors is needed. Various types of dynamic HTO models have been developed in many different countries. Joint international researches have been conducted many times for model comparisons and validations (BIOMOVS II, 1996a, 1996b). In 2003, however, with the understanding of an insufficiency in the validation test, the IAEA started on a joint international research program for the validation of environmental models (EMRAS : Environmental Modelling for Radiation Safety) as a successor to the BIOMASS (2001). The KAERI submitted 'a scenario of an acute soybean exposure to HTO' to the Tritium Working Group (Theme 1) in the EMRAS program. It was accepted as Task 2 of the working group. This report is the result of a joint research for the KAERI scenario carried out by the EMRAS tritium working group with the KAERI playing a role of a coordinator.

  12. Cooperation of nuclear manpower development between Viet Nam and Korea in order to enhance establishment of infrastructure in exporting nuclear technology to Viet Nam

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Park, J. K.; Kim, Y. T.; Nam, Y. M.; Jang, Y. H.; Yang, M. H

    2003-08-15

    Through this project, KAERI provided OJT Programme to 3 nuclear experts of Viet Nam at the KAERI for 3 months as a cooperation of human resource development in the field of nuclear policy, nuclear safety analysis and thermo hydraulic. We could have publicity activities of S/W and H/W then achieve an advantage position of economical and technical in exporting nuclear technology to Viet Nam. Also we have provided a training course and seminar for a high-level delegation of nuclear policy decision makers, which is consisted of 5 deputy ministers and general directors of Viet Nam in Korea. Thus we could have Vietnamese who are favoring Korea. The KAERI will also prepare a data base of trained Vietnamese in Korea for the maximum utilization of them in cooperating with Viet Nam. We accomplished the cooperation of human resource development and providing program and curriculum of the nuclear education and training in Viet Nam. Furthermore, it is expected that the enhancement of nuclear technical cooperation between Viet Nam and Korea and the nuclear human resource development.

  13. Korea-China Optical Technology Research Centre

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Cheol Jung; Cha, H. K.; Rhee, Y. J. (and others)

    2007-04-15

    The main objectives of this project are to develop cooperative channel by personnel exchanges between industrial, educational and research partners of Korea and China on the fields of optical technologies which are the basis of optical industry and being spot-lighted as new industry of 21th century, and to raise the class of Korean optical technology up to world class by utilization of Chinese large facilities through the cooperative research between the optical technology institutions of both sides. To attain the goals mentioned above, we carried out the cooperative researches between the Korean and Chinese optical technology institutions in the following 7 fields; ? research cooperation between KAERI-SITP for the quantum structured far-IR sensor technology - research cooperation for the generation of femtosecond nuclear fusion induced neutrons - research cooperation between KAERI-AIOFM for laser environment analysis and remote sensing technology - research cooperation between KAERI-SIOM for advanced diode-pumped laser technology - cooperative research related on linear and nonlinear magneto-optical properties of advanced magnetic quantum structures - design of pico-second PW high power laser system and its simulation and - cooperative research related on the femto-second laser-plasma interaction physics.

  14. Development of cold neutron depth profiling system at HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Park, B.G. [Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 151-744 (Korea, Republic of); Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 305-355 (Korea, Republic of); Sun, G.M., E-mail: gmsun@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 305-355 (Korea, Republic of); Choi, H.D. [Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 151-744 (Korea, Republic of)

    2014-07-01

    A neutron depth profiling (NDP) system has been designed and developed at HANARO, a 30 MW research reactor at the Korea Atomic Energy Research Institute (KAERI). The KAERI-NDP system utilizes cold neutrons that are transported along the CG1 neutron guide from the cold neutron source and it consists of a neutron beam collimator, a target chamber, a beam stopper, and charged particle detectors along with NIM-standard modules for charged particle pulse-height analysis. A 60 cm in diameter stainless steel target chamber was designed to control the positions of the sample and detector. The energy distribution of the cold neutron beam at the end of the neutron guide was calculated by using the Monte Carlo simulation code McStas, and a neutron flux of 1.8×10{sup 8} n/cm{sup 2} s was determined by using the gold foil activation method at the sample position. The performance of the charged particle detection of the KAERI-NDP system was tested by using Standard Reference Materials. The energy loss spectra of alpha particles and Li ions emitted from {sup 10}B, which was irradiated by cold neutrons, were measured. The measured peak concentration and the areal density of {sup 10}B in the Standard Reference Material are consistent with the reference values within 1% and 3.4%, respectively.

  15. Development of cold neutron depth profiling system at HANARO

    Science.gov (United States)

    Park, B. G.; Sun, G. M.; Choi, H. D.

    2014-07-01

    A neutron depth profiling (NDP) system has been designed and developed at HANARO, a 30 MW research reactor at the Korea Atomic Energy Research Institute (KAERI). The KAERI-NDP system utilizes cold neutrons that are transported along the CG1 neutron guide from the cold neutron source and it consists of a neutron beam collimator, a target chamber, a beam stopper, and charged particle detectors along with NIM-standard modules for charged particle pulse-height analysis. A 60 cm in diameter stainless steel target chamber was designed to control the positions of the sample and detector. The energy distribution of the cold neutron beam at the end of the neutron guide was calculated by using the Monte Carlo simulation code McStas, and a neutron flux of 1.8×108 n/cm2 s was determined by using the gold foil activation method at the sample position. The performance of the charged particle detection of the KAERI-NDP system was tested by using Standard Reference Materials. The energy loss spectra of alpha particles and Li ions emitted from 10B, which was irradiated by cold neutrons, were measured. The measured peak concentration and the areal density of 10B in the Standard Reference Material are consistent with the reference values within 1% and 3.4%, respectively.

  16. Analysis of Pending Problems for a Technology Demand of Domestic Operational Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Dae Seo; Park, Won Seok; Wi, Myung Hwan; Ha, Jae Joo

    2008-01-15

    Eleven technology fields were chosen, which have a relation with the solution of the pending problems of domestic operational nuclear power plants to manage an efficient operation and safe regulation for domestic nuclear power plants. The progressive background, requirements, and performance on the pending problems, 34, of an operation and regulation for domestic nuclear power plants were analyzed with regard to a risk information application, severe accident, PSR of structural materials, underwater monitoring, operation inspection and a fire protection, an instrument aging, metal integrity and steam generator, human technology and a digital I and C, quality assurance, secondary system and a user reliance and mass communications. KAERI's role is to provide a solution to these pending problems of domestic nuclear power plants. KAERI's technology is to be applicable to the pending problems for domestic nuclear power plants to raise an operational efficiency and an application frequency of nuclear power plants. In the future, a technology treaty between KAERI and KHNP is to be established to solve the pending problems for domestic nuclear power plants. Operation rate of nuclear power plants will also be raised and contribute to the supply of national energy due to this technology treaty.

  17. Numerical simulation of the direct contact condensation phenomena for PTS-related in single and combined-effect thermal hydraulic test facilities using TransAT CMFD code

    Energy Technology Data Exchange (ETDEWEB)

    Kadi, Rabah, E-mail: kadi.rkhaled@hotmail.com [Laboratory for Thermal-Hydraulics, Nuclear Research Center of Birine (Algeria); Aissani, Slimane [Hydrocarbons and Chemistry Faculty, University of Boumerdes (Algeria); Bouam, Abdellah [Laboratory for Thermal-Hydraulics, Nuclear Research Center of Birine (Algeria)

    2015-11-15

    Highlights: • TransAT CMFD code application to DCC phenomenon. • LEIS methodology to predict the condensing steam flow rate. • Validation of interfacial phase-change heat transfer and turbulence models. • Correction of damping function at the free surface region. • Numerical validation of previous models using LIM and KAERI & KAIST test facilities. - Abstract: The use of CFD for the industrial studies related to PTS, including DCC is already possible; improvements of the two-phase modeling capabilities have to be undertaken to qualify the codes for the simulation of such flows. The DCC in horizontally stratified flow regime constitutes very considerable challenge exercises for a computational fluid dynamics (CFD) simulation of the thermal hydraulics PTS phenomenon because the interplay between turbulence and interfacial heat and mass transfer problem. The main purpose of our study is to investigate numerically the DCC in horizontally stratified steam water flow in a 2D and 3D channel using TransAT CMFD code. The new methodology known as Large-Eddy & Interface (LEIS) have been implemented for treatment of turbulence combined with interface tracking ITM (level set approach). Among of the so-called ‘coarse-grained’ ITM's models, the modified original surface divergence has been chosen as well as the treatment of the turbulence by URANS and VLES. This contribution addressed on the validation of interfacial phase-change heat transfer and turbulence models with special correction of the damping function at the free surface for single and combined-effect thermal hydraulic studies for LIM and KAERI & KAIST test facilities. The LIES methodology was found to apply successfully to predict the condensing steam flow rate in the all cases of the LIM test case involving a Smooth to Wavy turbulent, concurrent stratified steam-water flow in a 2D channel. The CMFD TransAT code predicting capability is analyzed, comparing the liquid temperature and to much the

  18. Waste Information Management System-2012 - 12114

    Energy Technology Data Exchange (ETDEWEB)

    Upadhyay, H.; Quintero, W.; Shoffner, P.; Lagos, L.; Roelant, D. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States)

    2012-07-01

    The Waste Information Management System (WIMS) -2012 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. WIMS continues to successfully accomplish the goals and objectives set forth by DOE for this project. It has

  19. Waste Information Management System with 2012-13 Waste Streams - 13095

    Energy Technology Data Exchange (ETDEWEB)

    Upadhyay, H.; Quintero, W.; Lagos, L.; Shoffner, P.; Roelant, D. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States)

    2013-07-01

    The Waste Information Management System (WIMS) 2012-13 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)

  20. Error Reduction for Weigh-In-Motion

    Energy Technology Data Exchange (ETDEWEB)

    Hively, Lee M [ORNL; Abercrombie, Robert K [ORNL; Scudiere, Matthew B [ORNL; Sheldon, Frederick T [ORNL

    2009-01-01

    Federal and State agencies need certifiable vehicle weights for various applications, such as highway inspections, border security, check points, and port entries. ORNL weigh-in-motion (WIM) technology was previously unable to provide certifiable weights, due to natural oscillations, such as vehicle bouncing and rocking. Recent ORNL work demonstrated a novel filter to remove these oscillations. This work shows further filtering improvements to enable certifiable weight measurements (error < 0.1%) for a higher traffic volume with less effort (elimination of redundant weighing).

  1. Hanford inventory program user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Hinkelman, K.C.

    1994-09-12

    Provides users with instructions and information about accessing and operating the Hanford Inventory Program (HIP) system. The Hanford Inventory Program is an integrated control system that provides a single source for the management and control of equipment, parts, and material warehoused by Westinghouse Hanford Company in various site-wide locations. The inventory is comprised of spare parts and equipment, shop stock, special tools, essential materials, and convenience storage items. The HIP replaced the following systems; ACA, ASP, PICS, FSP, WSR, STP, and RBO. In addition, HIP manages the catalog maintenance function for the General Supplies inventory stocked in the 1164 building and managed by WIMS.

  2. Development of modern CANDU PHWR cross-section libraries for SCALE

    Energy Technology Data Exchange (ETDEWEB)

    Shoman, Nathan T., E-mail: nshoman@vols.utk.edu; Skutnik, Steven E., E-mail: sskutnik@utk.edu

    2016-06-15

    Highlights: • New ORIGEN libraries for CANDU 28 and 37-element fuel assemblies have been created. • These new reactor data libraries are based on modern ENDF/B-VII.0 cross-section data. • The updated CANDU data libraries show good agreement with radiochemical assay data. • Eu-154 overestimated when using ENDF-VII.0 due to a lower thermal capture cross-section. - Abstract: A new set of SCALE fuel lattice models have been developed for the 28-element and 37-element CANDU fuel assembly designs using modern cross-section data from ENDF-B/VII.0 in order to produce new reactor data libraries for SCALE/ORIGEN depletion analyses. These new libraries are intended to provide users with a convenient means of evaluating depletion of CANDU fuel assemblies using ORIGEN through pre-generated cross sections based on SCALE lattice physics calculations. The performance of the new CANDU ORIGEN libraries in depletion analysis benchmarks to radiochemical assay data were compared to the previous version of the CANDU libraries provided with SCALE (based on WIMS-AECL models). Benchmark comparisons with available radiochemical assay data indicate that the new cross-section libraries perform well at matching major actinide species (U/Pu), which are generally within 1–4% of experimental values. The library also showed similar or better results over the WIMS-AECL library regarding fission product species and minor actinoids (Np, Am, and Cm). However, a notable exception was in calculated inventories of {sup 154}Eu and {sup 155}Eu, where the new library employing modern nuclear data (ENDF/B-VII.0) performed substantially poorer than the previous WIMS-AECL library (which used ENDF-B/VI.8 cross-sections for these species). The cause for this discrepancy appears to be due to differences in the {sup 154}Eu thermal capture cross-section between ENDF/B-VI.8 and ENDF/B-VII.0, an effect which is exacerbated by the highly thermalized flux of a CANDU heavy water reactor compared to that of a

  3. IONIZED GAS IN THE FIRST 10 kpc OF THE INTERSTELLAR GALACTIC HALO: METAL ION FRACTIONS

    Energy Technology Data Exchange (ETDEWEB)

    Howk, J. Christopher [Department of Physics, University of Notre Dame, Notre Dame, IN 46556 (United States); Consiglio, S. Michelle, E-mail: jhowk@nd.edu, E-mail: smconsiglio@ucla.edu [Current address: Department of Physics and Astronomy, University of California, Los Angeles, Los Angeles, CA 90095 (United States)

    2012-11-10

    We present direct measures of the ionization fractions of several sulfur ions in the Galactic warm ionized medium (WIM). We obtained high-resolution ultraviolet absorption-line spectroscopy of post-asymptotic giant branch stars in the globular clusters Messier 3 [(l, b) = (42.{sup 0}2, +78.{sup 0}7), d = 10.2 kpc, and z = 10.0 kpc] and Messier 5 [(l, b) = (3.{sup 0}9, +46.{sup 0}8), d = 7.5 kpc, and z = +5.3 kpc] with the Hubble Space Telescope and Far Ultraviolet Spectroscopic Explorer to measure, or place limits on, the column densities of S I, S II, S III, S IV, S VI, and H I. These clusters also house millisecond pulsars, whose dispersion measures give an electron column density from which we infer the H II column in these directions. We find fractions of S{sup +2} in the WIM for the M 3 and M 5 sight lines x(S{sup +2}) {identical_to} N(S{sup +2})/N(S) = 0.33 {+-} 0.07 and 0.47 {+-} 0.09, respectively, with variations perhaps related to location. With negligible quantities of the higher ionization states, we conclude that S{sup +} and S{sup +2} account for all of the S in the WIM. We extend the methodology to study the ion fractions in the warm and hot ionized gas of the Milky Way, including the high ions Si{sup +3}, C{sup +3}, N{sup +4}, and O{sup +5}. The vast majority of the Galactic ionized gas is warm (T {approx} 10{sup 4} K) and photoionized (the WIM) or very hot (T > 4 Multiplication-Sign 10{sup 5} K) and collisionally ionized. The common tracer of ionized gas beyond the Milky Way, O{sup +5}, traces <1% of the total ionized gas mass of the Milky Way.

  4. Speech Recognition: Acoustic, Phonetic and Lexical Knowledge

    Science.gov (United States)

    2013-04-04

    v en 1 < 2 0 Ü e ® • >j> •> . - - ^^^S-J .* »-. -^ J O-’-r^ iOt -’BOlOOM 3g» » i.a jt a ’S S 2 u « g I ä o a S 3 9 « J ^ a...M.O — !M.O-^ )«.0 -...0 » 1 T i r*i—r ■ mm WIM, . 9.01 Fi(jure 3: Histogram . Standard Dev alien RECOGNH ION EXPER’.vIENT Alter

  5. Pressure tube creep impact on the physics parameters for CANDU-6 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kim, W. Y.; Min, B. J. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Kam, S. C.; Kim, M. E. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2004-07-01

    The lattice cell calculations are performed to assess the sensitivity of the reactor physics parameters to pressure tube creep resulting from radiation aging. The physics parameters of the lattice cell are calculated by using WIMSD-5B code, WIMS- AECL code, and MCNP code. The reference model(normal state) and two perturbed models accounting for the pressure tube creep are developed on the basis of CANDU-6 lattice cell. The 2.5% and 5% values of pressure tube diameter creep are considered. Also, The effects of the analyzed lattice parameters which are the coolant void reactivity, the fuel fission density and the atom density of Pu isotopes on the lattice.

  6. A Study of the Warm Ionized Medium Throughout the Sagittarius-Carina Arm

    CERN Document Server

    Krishnarao, Dhanesh; Benjamin, Robert A

    2016-01-01

    We present velocity-channel maps and analysis of the warm ionized medium (WIM) throughout the Sagittarius- Carina arm at Galactic longitudes 20 1000 pc along the far Carina arm. Physical conditions of the ionized gas are analyzed using the [S II]/H-alpha line ratio, which more closely traces H-alpha intensity than height above the plane, z, suggesting a stronger relationship with the in-situ electron density. We interpret this result as further evidence for the majority of the observed diffuse emission originating from in-situ ionized gas as opposed to scattered light from classical H II regions in the plane.

  7. A WEIGHTED ITERATIVE METHOD FOR ROBUST SELF-CALIBRATION

    Institute of Scientific and Technical Information of China (English)

    Liu Shigang; Wu Chengke; Tang Li; Jia Jing

    2006-01-01

    A robust self-calibration method is presented, which can efficiently discard the outliers based on a Weighted Iteration Method (WIM). The method is an iterative process in which the projective reconstruction is obtained based on the weights of all the points, whereas the weights are defined in inverse proportion to the reciprocal of the re-projective errors. The weights of outliers trend to zero after several iterations, and the accurate projective reconstruction is determined. The location of the absolute conic and the camera intrinsic parameters are obtained after the projective reconstruction. The theory and experiments with both simulate and real data demonstrate that the proposed method is very efficient and robust.

  8. Develop 3G Application with The J2ME SATSA API

    Science.gov (United States)

    JunWu, Xu; JunLing, Liang

    This paper describes research in the use of the Security and Trust Services API for J2ME (SATSA) to develop mobile applications. for 3G networks. SATSA defines a set of APIs that allows J2ME applications to communicate with and access functionality, secure storage and cryptographic operations provided by security elements such as smart cards and Wireless Identification Modules (WIM). A Java Card application could also work as an authentication module in a J2ME-based e-bank application. The e-bank application would allow its users to access their bank accounts using their cell phones.

  9. Analysis of the impact of coolant density variations in the high efficiency channel of a pressure tube super critical water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Scriven, M.G.; Hummel, D.W.; Novog, D.R.; Luxat, J.C. [McMaster Univ., Hamilton, Ontario (Canada)

    2012-07-01

    The Pressure Tube (PT) Supercritical Water Reactor (SCWR) is based on a light water coolant operating at pressures above the thermodynamic critical pressure; a separate low temperature and low pressure moderator. The coolant density changes by an order of magnitude depending on its local enthalpy in the porous ceramic insulator tube. This causes significant changes in the neutron transport characteristics, axially and radially, in the fuel channel. This work performs lattice physics calculations for a 78-element Pu-Th fuel at zero burnup and examines the effect of assumptions related to coolant density in the radial direction of a HEC, using the neutron transport code WIMS-AECL. (author)

  10. The interactive web-based program MSmonitor for self-management and multidisciplinary care in multiple sclerosis: utilization and valuation by patients

    OpenAIRE

    Jongen PJ; Sinnige LG; van Geel BM; Verheul F; Verhagen WI; van der Kruijk RA; Haverkamp R; Schrijver HM; Baart JC; Visser LH; Arnoldus EP; Gilhuis HJ; Pop P; Booy M; Heerings M

    2016-01-01

    Peter Joseph Jongen,1,2 Ludovicus G Sinnige,3 Björn M van Geel,4 Freek Verheul,5 Wim I Verhagen,6 Ruud A van der Kruijk,7 Reinoud Haverkamp,8 Hans M Schrijver,9 Jacoba C Baart,10 Leo H Visser,11 Edo P Arnoldus,12 Herman Jacobus Gilhuis,13 Paul Pop,14 Monique Booy,15 Marco Heerings,16 Anton Kool,17 Esther van Noort17 1Department of Community and Occupational Medicine, University Medical Center Groningen, University of Groningen, Groningen, 2MS4 Research Institute, Nijmegen, ...

  11. Bridge Influence Line Estimation for Bridge Weigh-in-Motion System

    OpenAIRE

    Ieng, Sio Song

    2015-01-01

    This paper presents an algorithm that estimates the influence line (IL) of a bridge using data collected when trucks pass over the sensors installed in the bridge. The algorithm is tested with data collected from the Millau Viaduct in France using a bridge weigh-in-motion (B-WIM) device. The algorithm uses the maximum likelihood estimation (MLE) and is compared with an old algorithm. The algorithm is more robust because it takes into account many signals for the estimation of the IL.

  12. Fragility Analysis Methodology for Degraded Structures and Passive Components in Nuclear Power Plants - Illustrated using a Condensate Storage Tank

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J.; Braverman, J.; Hofmayer, C.; Choun, Y.; Kim, M.; Choi, I.

    2010-06-30

    The Korea Atomic Energy Research Institute (KAERI) is conducting a five-year research project to develop a realistic seismic risk evaluation system which includes the consideration of aging of structures and components in nuclear power plants (NPPs). The KAERI research project includes three specific areas that are essential to seismic probabilistic risk assessment (PRA): (1) probabilistic seismic hazard analysis, (2) seismic fragility analysis including the effects of aging, and (3) a plant seismic risk analysis. Since 2007, Brookhaven National Laboratory (BNL) has entered into a collaboration agreement with KAERI to support its development of seismic capability evaluation technology for degraded structures and components. The collaborative research effort is intended to continue over a five year period. The goal of this collaboration endeavor is to assist KAERI to develop seismic fragility analysis methods that consider the potential effects of age-related degradation of structures, systems, and components (SSCs). The research results of this multi-year collaboration will be utilized as input to seismic PRAs. In the Year 1 scope of work, BNL collected and reviewed degradation occurrences in US NPPs and identified important aging characteristics needed for the seismic capability evaluations. This information is presented in the Annual Report for the Year 1 Task, identified as BNL Report-81741-2008 and also designated as KAERI/RR-2931/2008. The report presents results of the statistical and trending analysis of this data and compares the results to prior aging studies. In addition, the report provides a description of U.S. current regulatory requirements, regulatory guidance documents, generic communications, industry standards and guidance, and past research related to aging degradation of SSCs. In the Year 2 scope of work, BNL carried out a research effort to identify and assess degradation models for the long-term behavior of dominant materials that are

  13. Enhancement of weld failure and tube ejection model in PENTAP program

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Jaehoon; An, Sang Mo; Ha, Kwang Soon; Kim, Hwan Yeol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The reactor vessel pressure, the debris mass, the debris temperature, and the component of material can have an effect on the penetration tube failure modes. Furthermore, these parameters are interrelated. There are some representative severe accident codes such as MELCOR, MAAP, and PENTAP program. MELCOR decides on a penetration tube failure by its failure temperature such as 1273K simply. MAAP considers all penetration failure modes and has the most advanced model for a penetration tube failure model. However, the validation work against the experimental data is very limited. PENTAP program which evaluates the possible penetration tube failure modes such as creep failure, weld failure, tube ejection, and a long term tube failure under given accident condition was developed by KAERI. The experiment for the tube ejection is being performed by KAERI. The temperature distribution and the ablation rate of both weld and lower vessel wall can be obtained through the experiment. This paper includes the updated calculation steps for the weld failure and the tube ejection modes of the PENTAP program to apply the experimental results. PENTAP program can evaluate the possible penetration tube failure modes. It still requires a large amount of efforts to increase the prediction of failure modes. Some calculation steps are necessary for applying the experimental and the numerical data in the PENTAP program. In this study, new calculation steps are added to PENTAP program to enhance the weld failure and tube ejection models using KAERI's experimental data which are the ablation rate and temperature distribution of weld and lower vessel wall.

  14. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology-

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Lee, Yong Bum; Park, Soon Yong; Cho, Jae Wan; Lee, Nam Hoh; Kim, Woong Kee; Moon, Byung Soo; Kim, Seung Hoh; Kim, Chang Heui; Kim, Byung Soo; Hwang, Suk Yong; Lee, Yung Kwang; Moon, Je Sun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Main activity in this year is to develop both remote handling system and telepresence techniques, which can be used for people involved in extremely hazardous working area to alleviate their burden. In the robot vision technology part, KAERI-PSM system, stereo imaging camera module, stereo BOOM/MOLLY unit, and stereo HMD unit are developed. Also, autostereo TV system which falls under the category of next generation stereo imaging technology has been studied. The performance of KAERI-PSM system for remote handling task is evaluated and compared with other stereo imaging systems as well as general TV imaging system. The result shows that KAERI-PSM system is superior to the other stereo imaging systems about remote operation speedup and accuracy. The automatic recognition algorithm of instrument panel is studied and passive visual target tracking system is developed. The 5 DOF camera serving unit has been designed and fabricated. It is designed to function like human`s eye. In the sensing and intelligent control research part, thermal image database system for thermal image analysis is developed and remote temperature monitoring technique using fiber optics is investigated. And also, two dimensional radioactivity sensor head for radiation profile monitoring system is designed. In the part of intelligent robotics, mobile robot is fabricated and its autonomous navigation using fuzzy control logic is studied. These remote handling and telepresence techniques developed in this project can be applied to nozzle-dam installation/removal robot system, reactor inspection unit, underwater nuclear pellet inspection and pipe abnormality inspection. And these developed remote handling and telepresence techniques will be applied in general industry, medical science, and military as well as nuclear facilities. 203 figs, 12 tabs, 72 refs. (Author).

  15. Incorporating Level-2 PSA Feature of CONPAS into AIMS-PSA Software

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sang Hoon; Lim, Hogon; Ahn, Kwang Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    CONPAS (CONtainment Performance Analysis System) utilizes a methodology to treat containment phenomena in detail like APET but in simple way. In mid 2000's, KAERI has developed very fast cut set generator FTREX and PC's OS (Operating system) has changed into Windows 95. Thus, KAERI has developed new Level-1 PSA software, called AIMS-PSA (Advanced Information Management System for PSA) to replace KIRAP. Recently, KAERI has been developing an integrated PSA platform, called OCEANS (On-line Consolidator and Evaluator of All mode risk for Nuclear System), for the risk assessment of all power modes and all hazards. CONPAS for Level-2 PSA was developed in 1990's using the Visual Basic 6.0 compiler which is not supported any more. It needs to be updated for the integrated PSA software framework. This paper describes a study to incorporate the features of CONPAS into AIMS-PSA. The basic idea is to follow the approach of CONPAS, but in the integrated way. Various approaches for Level-2 PSA have been used since WASH-1400. APET approach of NUREG-1150 study would be most comprehensive and complex methodology for containment event tree analysis. CONPAS is the Level-2 PSA software to utilize an approach to treat containment phenomena in detail like APET but in simple way. But, new Level-2 PSA software is required to develop more integrated PSA framework. A modified approach of CONPAS is developed and incorporated in AIMS-PSA software that can handle Level-1 and Level-2 PSA in the integrated way (from the viewpoint of event tree and fault tree). AIMS-PSA combines whole Level-2 PSA model to produce a One Top fault tree and to generate cut sets in the same way as Level-1 PSA. Quantification results of Level-2 PSA such as frequency for each STC can be calculated from the minimal cut sets.

  16. Total System Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Yong Soo; Kang, Chul Hyung; Lee, Youn Myoung; Han, Ji Woong; Choi, Jong Won; Hahn, Pil Soo; Park, Jeong Hwa; Jeong, Mi Seon

    2007-06-15

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the

  17. Hydraulic characteristics of HANARO fuel bundles

    Energy Technology Data Exchange (ETDEWEB)

    Cho, S.; Chung, H. J.; Chun, S. Y.; Yang, S. K.; Chung, M. K. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    This paper presents the hydraulic characteristics measured by using LDV (Laser Doppler Velocimetry) in subchannels of HANARO, KAERI research reactor, fuel bundle. The fuel bundle consists of 18 axially finned rods with 3 spacer grids, which are arranged in cylindrical configuration. The effects of the spacer grids on the turbulent flow were investigated by the experimental results. Pressure drops for each component of the fuel bundle were measured, and the friction factors of fuel bundle and loss coefficients for the spacer grids were estimated from the measured pressure drops. Implications regarding the turbulent thermal mixing were discussed. Vibration test results measured by using laser vibrometer were presented. 9 refs., 12 figs. (Author)

  18. Development of the unified version of COBRA/RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, J. J.; Ha, K. S.; Chung, B. D.; Lee, W. J.; Sim, S. K. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The COBRA/RELAP5 code, an integrated version of the COBRA-TF and RELAP5/MOD3 codes, has been developed for the realistic simulations of complicated, multi-dimensional, two-phase, thermal-hydraulic system transients in light water reactors. Recently, KAERI developed an unified version of the COBRA/RELAP5 code, which can run in serial mode on both workstations and personal computers. This paper provides the brief overview of the code integration scheme, the recent code modifications, the developmental assessments, and the future development plan. 13 refs., 5 figs., 2 tabs. (Author)

  19. Analysis of ISO/IEC 17025 for establishment of KOLAS (Korea Laboratory Accreditation Scheme) quality assurance system

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Ji Hee

    2000-12-01

    Besides one existent accredited lab, radioactive material chemical analysis lab, five test laboratories and two calibration labs are under plan to acquire the accreditation from KOLAS. But the current Quality Manual was developed according to ISO Guide 25 that was superceded by ISO/IEC 17025. Since it is tailored to the radioactive material chemical analysis lab, a number of requirements of the Manual are not applicable to the labs other than radioactive material chemical analysis lab. Through the analysis of ISO/IEC 17025, a model of quality system was established which is not only consistent with ISO/IEC 17025 but reflective of the KAERI's situation.

  20. User`s manual ACE/ONED (Version 1.0)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ki Bok; Lee, Jeong Chan; Song, Jae Seung; Lee, Chang Kyu; Ji, Sung Kyun; Song, Jae Woong; Kim, Yong Rae; Chang, Jong Hwa [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of)

    1996-03-01

    This report explains installation of ACE/ONED code, structure of input and output, how to prepare input and introduces some sample inputs. ACE/ONED developed by KAERI is a two-group one-dimensional diffusion theory code for nuclear design and reactor simulations. The usage of ACE/ONED encompasses core follow calculation, load-following calculation, plant power control simulation, xenon oscillation simulation, control rod maneuvering, and so on. ACE/ONED programmed of FORTRAN 77 in most part can be run on almost all kinds of computer including personal computer. 4 tabs., 4 figs., 8 refs. (Author) .new.

  1. Advanced Risk Management and Monitoring System, ARMMS

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Yoo; Han, Sang Hoon; Lim, Ho Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-10-15

    Many risk informed regulation and applications (RIR and A) are approved and used for the nuclear power plants(NPPs), and more RIR and A will be actively applied in Korea. Also, since Korean NPPs are recently exported to other country such as UAE, RIR and A would be applied to the exported NPPs. Thus, a tool which will help the user apply RIR and A is required. KAERI is being developing a tool, called ARMMS (Advanced Risk Management and Monitoring System), for this purpose. The design plan of ARMMS was introduced in the Ref, and in this paper, the actual implementation of ARMMS is introduced, and the performance monitoring module is introduced

  2. Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Yong Moo; Jung, H. K.; Joo, Y. S.; Koo, K. M.; Hyung, H.; Sim, C. M.; Gong, U. S.; Kim, S. H.; Lee, J. P.; Rhoo, H. C.; Kim, M. S.; Ryoo, S. K.; Choi, C. H.; Oh, K. I

    1999-12-01

    One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (autho0008.

  3. Evaluation for the status of the IAEA inspection at Hanaro and TRIGA Mark II and III reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Sook; Lee, Byung Doo

    2007-11-15

    Safeguards implementation of nuclear material was carried out at facility level in an effect to support the peaceful nuclear activities in KAERI. Safeguards implementation is to fulfill the obligations associated with international agreements such as IAEA comprehensive safeguards agreement and additional protocol. IAEA inspection is the most important and basic factor of the safeguards implementation for the purpose of verifying whether all source or special fissionable material is diverted to nuclear weapons or other nuclear explosive devices. The status of the IAEA inspection at Hanaro and TRIGA Mark II and III reactor during 2001-2006 is evaluated in this report.

  4. KJRR-FAI Hydraulic Flow Testing Input Package

    Energy Technology Data Exchange (ETDEWEB)

    N.E. Woolstenhulme; R.B. Nielson; D.B. Chapman

    2013-12-01

    The INL, in cooperation with the KAERI via Cooperative Research And Development Agreement (CRADA), undertook an effort in the latter half of calendar year 2013 to produce a conceptual design for the KJRR-FAI campaign. The outcomes of this effort are documented in further detail elsewhere [5]. The KJRR-FAI was designed to be cooled by the ATR’s Primary Coolant System (PCS) with no provision for in-pile measurement or control of the hydraulic conditions in the irradiation assembly. The irradiation assembly was designed to achieve the target hydraulic conditions via engineered hydraulic losses in a throttling orifice at the outlet of the irradiation vehicle.

  5. Development of regulatory policy for SMART-P

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. H.; Lee, Y. H.; Moo, Philip; Koh, B. J.; Son, M. K.; Han, G. H.; Kim, D. H. [Korea Association for Nuclear Technology, Daejeon (Korea, Republic of)

    2004-06-15

    KAERI promoted the construction of a research reactor, SMART-P, the reduced scale of SMART, with intent to demonstrate the safety and performance of SMART. According to this progress, the development of regulatory process for SMART-P became necessary. The establishment of regulatory policy, based on the current regulatory guidelines as well as technical aspect, became essential matters. Considering the on-going small and medium size reactors in near future, the selection of the appropriate measure in the existing regulatory process to SMART-P is very important. Thus the schematic study for the applicable licensing procedure and regulatory requirements suitable for SMART-P is required.

  6. Elimination of noise peak for signal processing in Johnson noise thermometry development

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, I. G.; Moon, B. S.; Jeong, J. E.; Jeo, Y. H. [KAERI, Taejon (Korea, Republic of); Kisner, Roger A. [Oak Ridge National Lab., Oak Ridge (United States)

    2003-10-01

    The internal and external noise is the most considering obstacle in development of Johnson Noise Thermometry system. This paper addresses an external noise elimination issue of the Johnson Noise Thermometry system which is underway of development in collaboration between KAERI and ORNL. Although internal random noise is canceled by Cross Power Spectral Density function, a continuous wave penetrating into the electronic circuit is eliminated by the difference of peaks between Johnson signal and external noise. The elimination logic using standard deviation of CPSD and energy leakage problem in discrete CPSD function are discussed in this paper.

  7. Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Nie,J.; Braverman, J.; Hofmayer, C.; Kim, M. K.; Choi, I-K.

    2009-04-27

    When performing seismic safety assessments of nuclear power plants (NPPs), the potential effects of age-related degradation on structures, systems, and components (SSCs) should be considered. To address the issue of aging degradation, the Korea Atomic Energy Research Institute (KAERI) has embarked on a five-year research project to develop a realistic seismic risk evaluation system which will include the consideration of aging of structures and components in NPPs. Three specific areas that are included in the KAERI research project, related to seismic probabilistic risk assessment (PRA), are probabilistic seismic hazard analysis, seismic fragility analysis including the effects of aging, and a plant seismic risk analysis. To support the development of seismic capability evaluation technology for degraded structures and components, KAERI entered into a collaboration agreement with Brookhaven National Laboratory (BNL) in 2007. The collaborative research effort is intended to continue over a five year period with the goal of developing seismic fragility analysis methods that consider the potential effects of age-related degradation of SSCs, and using these results as input to seismic PRAs. In the Year 1 scope of work BNL collected and reviewed degradation occurrences in US NPPs and identified important aging characteristics needed for the seismic capability evaluations that will be performed in the subsequent evaluations in the years that follow. This information is presented in the Annual Report for the Year 1 Task, identified as BNL Report-81741-2008 and also designated as KAERI/RR-2931/2008. The report presents results of the statistical and trending analysis of this data and compares the results to prior aging studies. In addition, the report provides a description of U.S. current regulatory requirements, regulatory guidance documents, generic communications, industry standards and guidance, and past research related to aging degradation of SSCs. This report

  8. Safety analysis report for medical radioisotope transport cask

    Energy Technology Data Exchange (ETDEWEB)

    Seo, K. S.; Ku, J. H.; Lee, J. C. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-10-01

    KAERI has been producing radioisotopes for medical and industrial use and supplying them to radioisotope-using hospitals and industries. RI transport cask of A type package has been developed to transport medical radioisotopes from the HANARO to the hospitals. The safety analyses were performed under normal transport conditions in accordance with standards of transport regulations. As a results, it should be verified that the cask maintains the shielding and structural integrities under prescribed condition by the regulations. 8 refs., 20 figs., 7 tabs. (Author)

  9. Programs OPTMAN and SHEMMAN Version 6 (1999) - Coupled-Channels optical model and collective nuclear structure calculation -

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Jong Hwa; Lee, Jeong Yeon; Lee, Young Ouk; Sukhovitski, Efrem Sh. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-01-01

    Programs SHEMMAN and OPTMAN (Version 6) have been developed for determinations of nuclear Hamiltonian parameters and for optical model calculations, respectively. The optical model calculations by OPTMAN with coupling schemes built on wave functions functions of non-axial soft-rotator are self-consistent, since the parameters of the nuclear Hamiltonian are determined by adjusting the energies of collective levels to experimental values with SHEMMAN prior to the optical model calculation. The programs have been installed at Nuclear Data Evaluation Laboratory of KAERI. This report is intended as a brief manual of these codes. 43 refs., 9 figs., 1 tabs. (Author)

  10. Seismic base isolation technologies for Korea advanced liquid metal reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, B.; Lee, J.-H.; Koo, G.-H.; Lee, H.-Y.; Kim, J.-B. [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    2000-06-01

    This paper describes the status and prospects of the seismic base isolation technologies for Korea Advanced Liquid Metal Reactor (KALIMER). The research and development program on the seismic base isolation for KALIMER began in 1993 by KAERI under the national long-term R and D program. The objective of this program is to enhance the seismic safety, to accomplish the economic design, and to standardize the plant design through the establishment of technologies on seismic base isolation for liquid metal reactors. In this paper, tests and analyses performed in the program are presented. (orig.)

  11. Maintenance and fabrication of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chong Soo; Moon, Byung Soo; Hong, Suk Boong; Kim, Yong Keun; Kim, Jung Bok

    2000-12-01

    Providing technical support to the maintenance and repair problems of electronic instruments, we have assisted the research and development work, and reduced operation cost of the pilot plants in KAERI. In addition, we have improved the performance of the data processing system of RMS, and modified the cyclic box and IND100 using PLCs which are a facility for airborne monitoring in radiation area and lamp control modules of radiation monitoring control panel respectively. And also, a gamma-ray densitometer for KNGR has been designed and fabricated.

  12. Management of technical information department

    Energy Technology Data Exchange (ETDEWEB)

    Kim, T. H.; Han, D. H.; Moon, H. W. [and others

    1997-03-01

    This report introduces technical information activities in 1996. They are composed of basic tasks and applied tasks. 1. Basic activities - acquisition, cataloging, and Information services 2. Management of KAERI-TIPS (Technical Information Processing System) 3. Construction of the database for nuclear-related Information 4. Role of Specialized Nuclear Information Center in the field of nuclear energy and cooperation with INIS section of IAEA 5. Beside above activities, in 1996 TID homepage was opened and online document delivery service was provided. (author). 25 tabs., 17 figs.

  13. Development of regulatory policy for SMART-P

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. H.; Moon, S. H.; Lee, Y. H.; Son, M. K.; Han, K. H.; Kim, D. H. [Korea Association for Nuclear Technology, Taejon (Korea, Republic of)

    2003-06-15

    KAERI promoted the construction of a research reactor, SMART-P, the reduced scale of SMART, with intent to demonstrate the safety and performance of SMART. According to this progress, the development of regulatory process for SMART-P became necessary. The establishment of regulatory policy, based on the current regulatory guidelines as well as technical aspect, became essential matters. Considering the on-going small and medium size reactors m near future, the selection of the appropriate measure in the existing regulatory process to SMART-P is very important. Thus the schematic study for the applicable licensing procedure and regulatory requirements suitable for SMART-P is required.

  14. Insights from Development of Regulatory PSA Model for SMART

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Ju; Cho, Nam Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Kim, Inn Seock [ISSA Technology, Maryland (United States); Lee, Yong Suk [Seoul National University, Seoul (Korea, Republic of)

    2010-10-15

    SMART (System-Integrated Modular Advanced Reactor) is a first-of-the-kind integral reactor with 330 MW thermal power under active development by Korea Atomic Energy Research Institute (KAERI) for power generation and seawater desalination. SMART employs various design features that are not typically found in other nuclear power plants. Examples include a unique passive residual heat removal system (PRHRS), and enclosure of a pressurizer, eight helical steam generators, and eight canned reactor coolant pumps inside the reactor pressure vessel. This paper presents risk insights on the SMART reactor gained during the development of a regulatory PSA model by Korea Institute of Nuclear Safety (KINS)

  15. [C II] emission from galactic nuclei in the presence of X-rays

    CERN Document Server

    Langer, William D

    2015-01-01

    The luminosity of [C II] is used to probe the star formation rate in galaxies, but the correlation breaks down in some active galactic nuclei (AGNs). Models of the [C II] emission from galactic nuclei do not include the influence of X-rays on the carbon ionization balance, which may be a factor in reducing the [C II] luminosity. We calculate the [C II] luminosity in galactic nuclei under the influence of bright sources of X-rays. We solve the balance equation of the ionization states of carbon as a function of X-ray flux, electron, atomic hydrogen, and molecular hydrogen density. These are input to models of [CII] emission from the interstellar medium (ISM) in galactic nuclei. We also solve the distribution of the ionization states of oxygen and nitrogen in highly ionized regions. We find that the dense warm ionized medium (WIM) and dense photon dominated regions (PDRs) dominate the [C II] emission when no X-rays are present. The X-rays in galactic nuclei can affect strongly the C$^+$ abundance in the WIM con...

  16. Methods and Model Development for Coupled RELAP5/PARCS Analysis of the Atucha-II Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Andrew M. Ward

    2011-01-01

    Full Text Available In order to analyze the steady state and transient behavior of CNA-II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA-SA. Cross-sections for the coupled RELAP5/PARCS calculation were extracted from HELIOS within the GenPMAXS framework. The validation of both HELIOS and PARCS was performed primarily by comparisons to WIMS/PUMA and MCNP for idealized models. Special methods were developed to model the control rods and boron injection systems of CNA-II. The insertion of the rods is oblique, and a special routine was added to PARCS to treat this effect. CFD results combined with specialized mapping routines were used to model the boron injection system. In all cases there was good agreement in the results which provided confidence in the neutronics methods and modeling. A coupled code benchmark between U of M and U of Pisa is ongoing and results are still preliminary. Under a LOCA transient, the best estimate behavior of the core appears to be acceptable.

  17. Electromagnetism Mechanism for Enhancing the Refueling Cycle Length of a WWER-1000

    Directory of Open Access Journals (Sweden)

    Navid Poursalehi

    2017-02-01

    Full Text Available Increasing the operation cycle length can be an important goal in the fuel reload design of a nuclear reactor core. In this research paper, a new optimization approach, electromagnetism mechanism (EM, is applied to the fuel arrangement design of the Bushehr WWER-1000 core. For this purpose, a neutronic solver has been developed for calculating the required parameters during the reload cycle of the reactor. In this package, two modules have been linked, including PARCS v2.7 and WIMS-5B codes, integrated in a solver for using in the fuel arrangement optimization operation. The first results of the prepared package, along with the cycle for the original pattern of Bushehr WWER-1000, are compared and verified according to the Final Safety Analysis Report and then the results of exploited EM linked with Purdue Advanced Reactor Core Simulator (PARCS and Winfrith Improved Multigroup Scheme (WIMS codes are reported for the loading pattern optimization. Totally, the numerical results of our loading pattern optimization indicate the power of the EM for this problem and also show the effective improvement of desired parameters for the gained semi-optimized core pattern in comparison to the designer scheme.

  18. A fully integrated microbattery for an implantable microelectromechanical system

    Energy Technology Data Exchange (ETDEWEB)

    Albano, F. [Department of Material Science Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Mechanical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Lin, Y.S.; Blaauw, D.; Sylvester, D.M. [Department of Electrical Engineering and Computer Science, University of Michigan, Ann Arbor, MI 48109 (United States); Wise, K.D. [Department of Electrical Engineering and Computer Science, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Biomedical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Sastry, A.M. [Department of Material Science Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Biomedical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Mechanical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States)

    2008-12-01

    The Wireless Integrated Microsystems Engineering Research Center's Intraocular Sensor (WIMS-ERC IOS) was studied as a model system for an integrated, autonomous implantable device. In the present study, we had four objectives: (1) select and designing an optimized power supply for the WIMS-IOS; (2) develop a fabrication technique allowing small scale, low-cost, and integrable fabrication for CMOS systems, and experimentally demonstrate a microscopic power source; (3) map capacity and lifetime of several fabricated microbatteries; (4) determine the effects of miniaturization on capacity, lifetime and device architecture. Physical vapor deposition (PVD) was used to deposit thin layers ({<=}1 {mu}m) of metal sequentially onto glass substrates (SiO{sub 2}, as used in the device). To map the influence of size over cell capacity and cycle life, we fabricated and tested five stand-alone cells using a Solartron {sup registered} 1470E battery tester and a Maccor {sup registered} 4000 series tester. A sixth battery was fabricated to investigate the effects of system integration, variable discharge rate and size reduction simultaneously. The highest experimental capacity among the larger cells O(cm{sup 2}) was 100 {mu}Ah, achieved by IOS-C-1 at 250 {mu}A (1.4 C) discharge. Among O(mm{sup 2}) cells, IOS-M-1 achieved the highest capacity (2.75 {mu}Ah, {proportional_to}76% of theoretical) at 2.5 {mu}A discharge (0.7 C rate). (author)

  19. Design of an implantable power supply for an intraocular sensor, using POWER (power optimization for wireless energy requirements)

    Energy Technology Data Exchange (ETDEWEB)

    Albano, F. [Department of Material Science Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Chung, M.D. [Department of Mechanical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Blaauw, D.; Sylvester, D.M. [Department of Electrical Engineering and Computer Science, University of Michigan, Ann Arbor, MI 48109 (United States); Wise, K.D. [Department of Biomedical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Electrical Engineering and Computer Science, University of Michigan, Ann Arbor, MI 48109 (United States); Sastry, A.M. [Department of Biomedical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Material Science Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Mechanical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States)

    2007-06-30

    The reduction in size and power usage of MEMS (microelectromechanical systems) devices has enabled development of fully implantable medical devices [K.D. Wise, IEEE Eng. Med. Biol. Magaz. 24(5) (2005) 22-29], though major obstacles remain in developing devices of very small scale (<1 mm) [T. Simunic, L. Benini, G. De Micheli, IEEE Trans. Very Large Scale Integr. (VLSI) Syst. 9 (2001) 15-28]. One of the most challenging applications; an intraocular sensor (IOS) developed by the Wireless Integrated Micro-Systems-Engineering Research Center (WIMS-ERC) at The University of Michigan; is the subject of the present study. Our specific objectives are fourfold: (1) to model the power usage of an intraocular sensor (IOS); (2) to develop a methodology for optimization of Hybrid Implantable Power Systems (HIPS); (3) to apply the selection tool to identify candidate power systems; and (4) to establish a methodology to fabricate and test the performance of an optimized power supply. In the present study we fabricated and tested three different cells. For one of these, 10 complete discharge and recharge cycles were successfully obtained. The experimental capacity was 7.70 mAh (15% of theoretical) for a discharge rate of C/5. As part of future work, a microbattery will be built for the WIMS-ERC IOS and tested in a fully integrated testbed. (author)

  20. Nebular emission and the Lyman continuum photon escape fraction in CALIFA early-type galaxies

    CERN Document Server

    Papaderos, P; Vilchez, J M; Kehrig, C; Lehnert, M D; Ziegler, B; Sanchez, S F; Husemann, B; Monreal-Ibero, A; Garcia-Benito, R; Bland-Hawthorn, J; Coritjo, C; de Lorenzo-Caceres, A; del Olmo, A; Falcon-Barroso, J; Galbany, L; Iglesias-Paramo, J; Lopez-Sanchez, A R; Marquez, I; Molla, M; Mast, D; van de Ven, G; Wisotzki, L

    2013-01-01

    We use deep integral field spectroscopy data from the CALIFA survey to study the warm interstellar medium (WIM) of 32 nearby early-type galaxies (ETGs). We propose a tentative subdivision of our sample ETGs into two groups, according to their Ha equivalent width (EW) and Lyman continuum (LyC) photon escape fraction (PLF). Type i ETGs show nearly constant EWs and a PLF~0, suggesting that photoionization by post-AGB stars is the main driver of their faint extranuclear nebular emission. Type ii ETGs are characterized by very low, outwardly increasing EWs, and a PLF as large as ~0.9 in their centers. Such properties point to a low, and inwardly decreasing WIM density and/or volume filling factor. We argue that, because of extensive LyC photon leakage, emission-line luminosities and EWs are reduced in type ii ETG nuclei by at least one order of magnitude. Consequently, the line weakness of these ETGs is by itself no compelling evidence for their containing merely "weak" (sub-Eddington accreting) active galactic nu...

  1. A Study on the Nuclear Technology Policy

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. J.; Lim, C. Y.; Yang, M. H. (and others)

    2008-03-15

    The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, changes of international nuclear energy policy environment and trends of nuclear technology development was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy environment surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed trends of nuclear technology policies and (2) developed the nuclear energy R and D innovation strategies. To put it in more detail, each subject was further explored as follows; (1) themes to analyze trends of nuclear policies: nuclear Renaissance and forecast for nuclear power plant, International collaboration for advanced nuclear technologies in GIF, INPRO and I-NERI, The present situation and outlook for world uranium market (2) themes to develop of nuclear energy R and D innovation strategies: The mid-term strategy plan of the KAERI, The technological innovation case of the KAERI.

  2. Development and Enhancement of Web-based Nuclear Education System and It's Enhancement

    Energy Technology Data Exchange (ETDEWEB)

    Rho, Sipyo; Lee, K. B.; Nam, Y. M; Kim, H. K.; Hwang, I. A.; Yang, S. W.; Nam, J. S.; Yoo, H. W.

    2012-02-15

    To deliver rapidly changing technologies effectively and economically, E-learning in the field of nuclear technology is being done gradually. In the first year of this project, 'Development and Enhancement of Web-based Nuclear Education System; we had established a server system, fitting-up several home pages in NTC(Nuclear Training and Education Center in KAERI) and newly developed LMS(Learning Management System). We had selected a MOODLE for it is one of popular open source in LMS field, and connected to the ANENT(Asian Nuclear in Education for Nuclear Technology) web portal, which is co-operating with IAEA/NKM. We had produced e-learning content mainly composed of the video clip that was taken by making a film of the lecturing in the course of training and education in NTC. The running time of the content is 100 hours totally. This e-learning content is going to reinforce by adding quiz and Q and A. Another activity is web-conferencing between NWU in South Africa and KAERI, which executed 4 times successfully. We are going to make a pre-course for the foreigners who will take part in our training and education course.

  3. Alternative Fabrication of Recycling Fast Reactor Metal Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ki-Hwan; Kim, Jong Hwan; Song, Hoon; Kim, Hyung-Tae; Lee, Chan-Bock [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Metal fuels such as U-Zr/U-Pu-Zr alloys have been considered as a nuclear fuel for a sodium-cooled fast reactor (SFR) related to the closed fuel cycle for managing minor actinides and reducing a high radioactivity levels since the 1980s. In order to develop innovative fabrication method of metal fuel for preventing the evaporation of volatile elements such as Am, modified casting under inert atmosphere has been applied for metal fuel slugs for SFR. Alternative fabrication method of fuel slugs has been introduced to develop an improved fabrication process of metal fuel for preventing the evaporation of volatile elements. In this study, metal fuel slugs for SFR have been fabricated by modified casting method, and characterized to evaluate the feasibility of the alternative fabrication method. In order to prevent evaporation of volatile elements such as Am and improve quality of fuel slugs, alternative fabrication methods of metal fuel slugs have been studied in KAERI. U-10Zr-5Mn fuel slug containing volatile surrogate element Mn was soundly cast by modified injection casting under modest pressure. Evaporation of Mn during alternative casting could not be detected by chemical analysis. Mn element was most recovered with prevention of evaporation by alternative casting. Modified injection casting has been selected as an alternative fabrication method in KAERI, considering evaporation prevention, and proven benefits of high productivity, high yield, and good remote control.

  4. The development of basic technology for instrumentation and control in NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Ham, Chang Shik; Park, Jae Chang; Kim, Jung Taek; Lee, Dong Young; Jung, Chul Hwan; Hwang, In Koo; Kim, Jung Soo; Kim, Chang Hwoi; Na, Nan Ju; Kim, Inn S.; Park, Kee Yong

    1997-07-01

    The PWR plant operation is normally categorized into plant startup, low power operation, normal operation, cooldown operation. In these operation, however, startup and cooldown operation is performed manually according to the operation procedure. These manual operation is required to operator`s technical skills. And the manual operation can be occurred to operational errors because of operator`s workload during long duration. Automatic startup system, named by Automatic Startup Intelligent Control System (ASICS) is developed for reducing operator tasks, optimizing heatup operation, and enhancement of operation reliability and availability from cold shutdown to reactor power 5%. ADIOS has applied several alarm processing technologies, such as plant mode dependency, state dependence, direct precursor, and level precursor, etc. ADIOS has also applied a model-base diagnostic functions for operator to cope with major transients. To confirm a correctness of alarm processing techniques, prototype have been developed based on KORI 3 and YGN 3 PWR NPPs. The about 3000 alarm objects have been represented as knowledge base in the prototypes. The alarm window like tile for the safety-related alarms, primary and secondary schematic display, and detailed system-level schematic display have been designed. Also ADIOS prototype based on YGN 3 PWR has evaluated a performance of human factor engineering using KAERI-ITF (KAERI-Integrated Test Facility). (author). 72 refs., 32 tabs., 85 figs.

  5. Basic Research on Selecting ISDC Activity for Decommissioning Costing in KRR-2 Decommissioning Project Experience Data

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Hee-Seong; Jin, Hyung-Gon; Park, Seung-Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    KAERI is performing research for calculation of expected time of a decommissioning work and evaluation of decommissioning cost and this research calculate a decommissioning work unit productivity based on the experience data of decommissioning activity for KRR-2. The KAERI be used to calculate the decommissioning cost and manage the experience data from the decommissioning activity through the Decommissioning Information Management System (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), and Decommissioning Work-unit Productivity Calculation System (DEWOCS). In this paper, the methodology was presented how select the ISDC activities in dismantling work procedures of a 'removal of radioactive concrete'. The reason to select the 'removal of radioactive concrete' is main key activity and generates the amount of radioactive waste. This data will take advantage of the cost estimation after the code for the selected items derived ISDC. There are various efforts for decommissioning costing in each country. In particular, OECD/NEA recommends decommissioning cost estimation using the ISDC and IAEA provides for Cost Estimation for Research Reactors in Excel (CERREX) program that anyone is easy to use the cost evaluation from a limited decommissioning experience in domestic. In the future, for the decommissioning cost evaluation, the ISDC will be used more widely in a strong position. This paper has described a method for selecting the ISDC item from the actual dismantling work procedures.

  6. Technology Development of an Advanced Small-scale Microchannel-type Process Heat Exchanger (PHE) for Hydrogen Production in Iodine-sulfur Cycle

    Energy Technology Data Exchange (ETDEWEB)

    Sah, Injin; Kim, Chan Soo; Kim, Yong Wan; Park, Jae-Won; Kim, Eung-Seon; Kim, Min-Hwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    In this study, ongoing manufacturing processes of the components employed in an advanced small-scale microchannel-type PHE are presented. The components, such as mechanically machined microchannels and a diffusion-bonded stack are introduced. Also, preliminary studies on surface treatment techniques for improving corrosion resistance from the corrosive sulfuric environment will be covered. Ongoing manufacturing process for an advanced small-size microchannel-type PHE in KAERI is presented. Through the preliminary studies for optimizing diffusion bonding condition of Hastelloy-X, a diffusion-bonded stack, consisting of primary and secondary side layer by layer, is scheduled to be fabricated in a few months. Also, surface treatment for enhancing the corrosion resistance from the sulfuric acid environment is in progress for the plates with microchannels. A massive production of hydrogen with electricity generation is expected in a Process Heat Exchanger (PHE) in a Very High Temperature gas-cooled Reactor (VHTR) system. For the application of hydrogen production, a small-scale gas loop for feasibility testing of a laboratory-scale has constructed and operated in Korea Atomic Energy Research Institute (KAERI) as a precursor to an experimental- and a pilot-scale gas loops.

  7. Development of the core safety regulation technology for the SMART-P

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Nam Zin; Kim, Do Sam; Lee, Kyeong Taek; Park, Young Ryoung; Lee, Gil Soo; Kim, Jong Woon; Yun, Sung Hwan; Lee, Jae Jun; Lee, Myung Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2003-06-15

    As the SMART-P is different from existing general reactors, new regulation technology is required to understand and assess the SMART-P for its regulatory reviews. One of the these technologies is related to the core design analysis. Because the SMART-P used metallic fuels, this study also collects general metallic nuclear fuel data and SMART-P's metallic fuel data from the materials studied by KAERI. The core design methodologies of KWU, ABB-CE, Westinghouse, Studsvik, Scandpower, US NRC and domestic research centers were investigated. Specially, The Hellios lattice core was studied for hexagonal nuclear fuel assembly calculation. Also, the VVER-1000 benchmark problem was analyzed by the PARCS code which has been developed by U.S. NRC. In this study, a AFEN-based computing code KORDAX os developed for the regulatory review of the SMART-P. KORDAX which is a nodal code using AFEN method dose not use transverse integration and this it can give higher accuracy results. Also, Because KORDAX is useful for hexagonal core and uses a method different with the core design code of the SMART-P developed by KAERI, it is judged that KORDAX can be an independent and reliable regulation verification code. In the next year study, HELIOS will be further studied as a core lattice code, and a hexagonal kinetics code which is based on AFEN method will be developed more systematically.

  8. Current and anticipated uses of thermal hydraulic codes in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyung-Doo; Chang, Won-Pyo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-07-01

    In Korea, the current uses of thermal hydraulic codes are categorized into 3 areas. The first application is in designing both nuclear fuel and NSSS. The codes have usually been introduced based on the technology transfer programs agreed between KAERI and the foreign vendors. Another area is in the supporting of the plant operations and licensing by the utility. The third category is research purposes. In this area assessments and some applications to the safety issue resolutions are major activities using the best estimate thermal hydraulic codes such as RELAP5/MOD3 and CATHARE2. Recently KEPCO plans to couple thermal hydraulic codes with a neutronics code for the design of the evolutionary type reactor by 2004. KAERI also plans to develop its own best estimate thermal hydraulic code, however, application range is different from KEPCO developing code. Considering these activities, it is anticipated that use of the best estimate hydraulic analysis code developed in Korea may be possible in the area of safety evaluation within 10 years.

  9. Growth and fabrication method of CdTe and its performance as a radiation detector

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hyojeong [Korea Atomic Energy Research Institute, Jeong-eup (Korea, Republic of); Sungkyunkwan University, Suwon (Korea, Republic of); Jeong, Manhee; Kim, Hansoo; Kim, Youngsoo; Ha, Jangho [Korea Atomic Energy Research Institute, Jeong-eup (Korea, Republic of); Chai, Jong-Seo [Sungkyunkwan University, Suwon (Korea, Republic of)

    2015-01-15

    A CdTe crystal ingot doped with 2000 ppm of Cl was grown by using the low-pressure Bridgman (LPB) method at the Korea Atomic Energy Research Institute (KAERI). A Semiconductor detector as a radiation detection sensor with a size of 7 (W) x 6.5 (D) x 2 (H) mm{sup 3} was fabricated from the CdTe ingot. In addition, the properties of the CdTe sample were observed through four kinds of experiments to analyze its performance. The resistivity was obtained as 1.41 x 10{sup 10} Ωcm by using a Keithley 6517A high-precision electrometer. The mobility-life time products for electrons and holes were 3.137 x 10{sup -}'4 cm{sup 2}/V and 4.868 x 10{sup -5} cm{sup 2}/V, respectively. Finally, we achieved a 16.8% energy resolution at 59.5 keV for the {sup 241}Am gamma-ray source. The CdTe semiconductor detector grown at KAERI has a performance good enough to detect low-energy gamma-rays.

  10. Comparison of Thermal Creep Strain Calculation Results Using Time Hardening and Strain Hardening Rules

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Junehyung; Cheon, Jinsik; Lee, Byoungoon; Lee, Chanbock [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    One of the design criteria for the fuel rod in PGSFR is the thermal creep strain of the cladding, because the cladding is exposed to a high temperature for a long time during reactor operation period. In general, there are two kind of calculation scheme for thermal creep strain: time hardening and strain hardening rules. In this work, thermal creep strain calculation results for HT9 cladding by using time hardening and strain hardening rules are compared by employing KAERI's current metallic fuel performance analysis code, MACSIS. Also, thermal creep strain calculation results by using ANL's metallic fuel performance analysis code, LIFE-METAL which adopts strain hardening rule are compared with those by using MACSIS. Thermal creep strain calculation results for HT9 cladding by using time hardening and strain hardening rules were compared by employing KAERI's current metallic fuel performance analysis code, MACSIS. Also, thermal creep strain calculation results by using ANL's metallic fuel performance analysis code, LIFE-METAL which adopts strain hardening rule were compared with those by using MACSIS. Tertiary creep started earlier in time hardening rule than in strain hardening rule. Also, calculation results by MACSIS with strain hardening and those obtained by using LIFE-METAL were almost identical to each other.

  11. Material properties of Grade 91 steel at elevated temperature and their comparison with a design code

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyeong Yeon; Kim, Woo Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Han Sang; Kim, Yun Jae [Korea Univ., Seoul (Korea, Republic of)

    2013-10-15

    In this study, the material properties of tensile strength, creep properties, and creep crack growth model for Gr.91 steel at elevated temperature were obtained from material tests at KAERI, and the test data were compared with those of the French elevated temperature design code, RCC-MRx. The conservatism of the material properties in the French design code is highlighted. Mod.9Cr-1Mo (ASME Grade 91; Gr.91) steel is widely adopted as candidate material for Generation IV nuclear systems as well as for advanced thermal plants. In a Gen IV sodium-cooled fast reactor of the PGSFR (Prototype Gen IV Sodium-cooled Fast Reactor) being developed by KAERI (Korea Atomic Energy Research Institute), Gr.91 steel is selected as the material for the steam generator, secondary piping, and decay heat exchangers. However, as this material has a relatively shorter history of usage in an actual plant than austenitic stainless steel, there are still many issues to be addressed including the long-term creep rupture life extrapolation and ratcheting behavior with cyclic softening characteristics.

  12. Design Features of the Separate Effect Test Facility for a Forced-Draft Sodium-to-Air Heat Exchanger (FHX) with Helical Finned Tubes

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyungmo; Eoh, Jaehyuk; Ko, Yung Joo; Cho, Youngil; Kim, Jong-Man; Lee, Hyeong-Yeon; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    A sodium-cooled fast reactor (SFR) is one of the most promising options to pursue these purposes, and the Korea Atomic Energy Research Institute (KAERI) is currently developing a PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor) with a pool-type reactor vessel. Among the many components in an SFR, a decay heat removal system (DHRS) is very important for a safety of nuclear power plants. The PGSFR adopted two different kinds of DHRS: an active and passive DHRS, and the decay heat from the primary sodium pool is moved to the two kinds of sodium-to-air heat exchangers as ultimate heat sinks through sodium-to-sodium decay heat exchangers (DHX). To verify the cooling performances and thermal-hydraulic characteristics of this type of heat exchanger, a separate effect sodium test facility named as SELFA (Sodium thermal-hydraulic Experiment Loop for Finned-tube sodium-to-Air heat exchanger) is being developed. The purposes of SELFA are verification and validation of the design code for FHX. For this, scales and configurations of SELFA are carefully defined as similarity with the FHX in the PGSFR. In this paper, we propose the key design features of SELFA including the model FHX (M-FHX) unit. To verify and validate a design code of the FHX in PGSFR, a separate effect test facility called as SELFA has being developed in KAERI.

  13. Clinical trial of {sup 165}Dy-HMA and {sup 166}Ho-CHICO in the treatment of Rheumatoid knee synovitis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. Y.; Yoo, D. H.; Bae, S. C.; Jun, J. B. [Hanyang University, Seoul (Korea, Republic of); Lim, S. M.; Hong, S. W.; Lee, S. Y.; Cheon, D. G.; Kim, S. J. [Korea Cancer Center Hospital, Seoul (Korea, Republic of)

    1997-07-01

    The untreated, chronic synovial inflammation leads to pannus formation and eventual destruction of the articular cartilage. In cases where medical therapy was unsuccessful, surgical or radiation synovectomy is necessary especially in the knee joints. The advantages of radiation synovectomy over surgical synovectomy are (1) greater destruction of diseased synovium, (2) reduced potential for blood clots and infection, (3) no requirement for anesthesia, and (4) less costly and less time consuming. Recently KAERI developed Dy-165 HMA, which was characterized by the absence of iron and a higher concentration of dysprosium. And then more recently KAERI also developed {sup 166}Ho-CHICO, which was characterized by relatively longer half-life(26.8 hr), more biological due to organic nature of chitosan, more even spatial distribution due to colloidal solution and more absorbable to synovium than Dy-165 HMA. We studied to evaluate the efficacy and safety of radiation synovectomy with Dy-165 HMA and {sup 166}Ho-CHICO in chronic rheumatoid synovitis with knee. The present study indicates that the Dy-165 HMA and {sup 166}Ho-CHICO are an effective and safe agent for radiation synovectomy. But further large scaled long-term follow up study and controlled study with steroid only are required. 15 refs. (author)

  14. Clinical trial of {sup 166}Ho-CHICO in the treatment of rheumatoid knee synovitis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. Y.; Yoo, D. H.; Bae, S. C.; Lee, I. H.; Jung, S. S.; Jun, J. B.; Kim, T. H.; Kim, S. S. [Hanyang Univ., Seoul (Korea)

    2000-03-01

    The untreated, chronic synovial inflammation leads to pannus formation and eventual destruction of the articular cartilage. In cases where medical therapy was unsuccessful, surgical of radiation synovectomy over surgical synovectomy are (1) greater destruction of diseased synovium, (2) reduced Potential for blood clots and infection, (3) no requirement for anesthesia, and (4) less costly and less time consuming. Recently KAERI developed Dy-165 HMA, which was characterized by the absence of iron and a higher concentration of dysprosium. And then more recently KAERI also developed {sup 16H}o-CHICO, which was characterized by relatively longer half-life (26.8 hr), more biological due to organic nature of chitosan, more even spatial distribution due to colloidal solution, and more absorbable to synovium than Dy-165 HMA. These long-term follow-up results indicate that the {sup 166}Ho-CHICO is an effective and safe agent for radiation synovectomy for knee synovitis in patients with rheumatoid arthritis as well as the other chronic arthritides. But further large scaled and controlled study are required. 16 refs. (Author)

  15. A state of the art on coastal environmental protection using radioisotope tracer technology

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Sung Hee; Jin, Joon Ha; Kim, Jong Bum; Choi, Byung Jong

    2002-04-01

    Construction of artificial structures has caused a sediment process change due to the variation of hydraulic condition in Korea. Subsequently we have a serious problem of shoaling for shoreline deformation, siltation of the harbor and shipping channel. To protect those abnormal environmental changes, a large estimate has been spent for additional construction such as outer wall facilities, littoral nourishment and dredging. Systematic long-term studies should be carried out to understand the causes of environmental change. In addition, comprehensive plan is required for its monitoring and prevention. The radioisotope application studies for coastal environmental protection have not been actively performed only in the developed countries like France, Canada, and Australia etc., but also in many developing countries like Poland, India. Since KAERI has performed two experiments in costal area of Korea in 1960s, no more study has been reported. Recently the studies of radiotracer application technology is getting more interested in terms of on-line data acquisition and analysis for the validation of the numerical simulation models. The experiment using radiotracer becomes an important part of the method to solve the problems happening in coastal environment, as it supplies data with high confidence in the field. On the basis of the experience obtained from the researches for industrial application of radiotracer technology, KAERI is going to make its first step to the development of the radiotracer technology for costal environmental studies.

  16. Demonstration of long-pulse acceleration of high power positive ion beam with JT-60 positive ion source in Japan–Korea joint experiment

    Energy Technology Data Exchange (ETDEWEB)

    Kojima, A., E-mail: kojima.atsushi@jaea.go.jp [Japan Atomic Energy Agency, Naka (Japan); Hanada, M. [Japan Atomic Energy Agency, Naka (Japan); Jeong, S.H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Bae, Y.S. [National Fusion Research Institute, Daejeon (Korea, Republic of); Chang, D.H.; Kim, T.S.; Lee, K.W.; Park, M.; Jung, B.K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Mogaki, K.; Komata, M.; Dairaku, M.; Kashiwagi, M.; Tobari, H.; Watanabe, K. [Japan Atomic Energy Agency, Naka (Japan)

    2016-01-15

    The long-pulse acceleration of the high-power positive ion beam has been demonstrated with the JT-60 positive ion source in the joint experiment among Japan Atomic Energy Agency (JAEA), Korea Atomic Energy Research Institute (KAERI) and National Fusion Research Institute (NFRI) under the collaboration program for the development of plasma heating and current drive systems. In this joint experiment, the increase of the heat load and the breakdowns induced by the degradation of the beam optics due to the gas accumulation was one of the critical issues for the long-pulse acceleration. As a result of development of the long-pulse operation techniques of the ion source and facilities of the neutral beam test stand in KAERI, 2 MW 100 s beam has been achieved for the first time. The achieved beam performance satisfies the JT-60SA requirement which is designed to be a 1.94 MW ion beam power from an ion source corresponding to total neutral beam power of 20 MW with 24 ion sources. Therefore, it was found that the JT-60 positive ion sources were applicable in the JT-60SA neutral beam injectors. Moreover, because this ion source is planned to be a backup ion source for KSTAR, the operational region and characteristic has been clarified to apply to the KSTAR neutral beam injector.

  17. A Study on the Tritium Behavior in the Rice Plant after a Short-Term Exposure of HTO

    Energy Technology Data Exchange (ETDEWEB)

    Yook, D-S.; Lee, K. J.; Choi, Y-H.

    2002-02-26

    In many Asian countries including Korea, rice is a very important food crop. Its grain is consumed by humans and its straw is used to feed animals. In Korea, there are four CANDU type reactors that release relatively large amounts of tritium into the environment. Since 1997, KAERI (Korea Atomic Energy Research Institute) has carried out the experimental studies to obtain domestic data on various parameters concerning the direct contamination of plant. In this study, the behavior of tritium in the rice plant is predicted and compared with the measurement performed at KAERI. Using the conceptual model of the soil-plant-atmosphere tritiated water transport system which was suggested by Charles E. Murphy, tritium concentrations in the soil and in leaves to time were derived. If the effect of tritium concentration in the soil is considered, the tritium concentration in leaves is described as a double exponential model. On the other hand if the tritium concentration in the soil is disregarded, the tritium concentration in leaves is described by a single exponential term as other models (e.g. Belot's or STAR-H3 model). Also concentration of organically bound tritium in the seed is predicted and compared with measurements. The results can be used to predict the tritium concentration in the rice plant at a field around the site and the ingestion dose following the release of tritium to the environment.

  18. Fabrication of particulate metal fuel for fast burner reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Ho Jin; Lee, Sun Yong; Kim, Jong Hwan; Woo, Yoon Myung; Ko, Young Mo; Kim, Ki Hwan; Park, Jong Man; Lee, Chan Bok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    U Zr metallic fuel for sodium cooled fast reactors is now being developed by KAERI as a national R and D program of Korea. In order to recycle transuranic elements (TRU) retained in spent nuclear fuel, remote fabrication capability in a shielded hot cell should be prepared. Moreover, generation of long lived radioactive wastes and loss of volatile species should be minimized during the recycled fuel fabrication step. Therefore, innovative fuel concepts should be developed to address the fabrication challenges pertaining to TRU while maintaining good performances of metallic fuel. Particulate fuel concepts have already been proposed and tested at several experimental fast reactor systems and vipac ceramic fuel of RIAR, Russia is one of the examples. However, much less work has been reported for particulate metallic fuel development. Spherical uranium alloy particles with various diameters can be easily produced by the centrifugal atomization technique developed by KAERI. Using the atomized uranium and uranium zirconium alloy particles, we fabricated various kinds of powder pack, powder compacts and sintered pellets. The microstructures and properties of the powder pack and pellets are presented.

  19. Comparison of SMART-SDA and SMART-PSS Behaviors Using an SBLOCA Scenario

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Doo Hyuk; Ko, Yung Joo; Suh, Jae Seung [System Engineering and Technology Co., Ltd., Daejeon (Korea, Republic of); Park, Hyun Sik; Moon, Sang Ki; Park, Rae Joon; Yi, Sung Jae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    In this study, an analysis of an SBLOCA scenario of safety injection line break accident was performed using the MARS-KS code to understand the general behavior between the SMART-SDA and the SMART-PSS design. An SBLOCA for the safety injection line break has been analyzed using the MARS-KS code to compare the thermal-hydraulic behaviors between the SMARTSDA and SMART-PSS. The present comparison analysis provides good insight into the passive safety system design features of the SMART-PSS and the thermal-hydraulics characteristic of the SMART design. It was found that the SMART-PSS has sufficient emergency core cooling capability during the transient period. Further study will be focused on the transient time. It should be able to compute the problem during 72 hours without AC power or operator action after an accident. SMART has been developed by KAERI, and SMART-Standard Design Approval (SDA) was recently granted in 2012. A SMART-Passive Safety System (PSS) is being developed by KAERI to improve the safety system. Active safety systems such as safety injection pumps will be replaced by a passive safety system, which is actuated only by the gravity force caused by the height difference. All tanks for the passive safety systems are higher than the injection nozzle, which is located around the reactor coolant pumps (RCPs)

  20. Consideration of ISDC for Decommissioning Cost Estimation

    Energy Technology Data Exchange (ETDEWEB)

    Cho, W. H.; Park, S. K.; Choi, Y. D.; Kim, I. S.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    In 2009, they decided to update the Yellow Book, and began to update it by analyzing user experiences. They found that several countries have adopted the proposed standardized cost structure for the production of cost estimates directly or for mapping national estimates onto a common structure. They also made conclusions that more detailed advice should be given on the use of the standardized structure and on the definition of cost items to avoid ambiguity. The revised cost structure, to be known as the International Structure for Decommissioning Costing (ISDC), was published in 2012. The standardized cost structure developed in the report may be used for estimating the costs of decommissioning of any type of nuclear facility. We analyzed this standardized cost structure (ISDC) and applied it to DECOMMIS which was developed by KAERI. The appropriate estimation system for domestic application was examined by comparing the estimation results. KAERI made WBS code in DECOMMIS and data obtained during decommissioning work of KRR2 and UCP. Recently the IAEA updated the decommissioning cost items and its structure by ISDC. The cost estimation items of the DECOMMIS were applied to ISDC structure. For applying, the ISDC code compared with WBS code of DECOMMIS as on text of the activity name from daily report basis. The mapping result of the ISDC items to WBS code of the DECOMMIS is much different. AS results of this study that it need the corresponding cost category which classified in accordance with the national standard price estimates.

  1. Perform Tests and Document Results and Analysis of Oxide Layer Effects and Comparisons

    Energy Technology Data Exchange (ETDEWEB)

    Collins, E. D. [ORNL; DelCul, G. D. [ORNL; Spencer, B. B. [ORNL; Hunt, R. D. [ORNL; Ausmus, C. [ORNL

    2014-08-30

    During the initial feasibility test using actual used nuclear fuel (UNF) cladding in FY 2012, an incubation period of 30–45 minutes was observed in the initial dry chlorination. The cladding hull used in the test had been previously oxidized in a dry air oxidation pretreatment prior to removal of the fuel. The cause of this incubation period was attributed to the resistance to chlorination of an oxide layer imparted by the dry oxidation pretreatment on the cladding. Subsequently in 2013, researchers at the Korea Atomic Energy Institute (KAERI) reported on their chlorination study [R1] on ~9-gram samples of unirradiated ZirloTM cladding tubes that had been previously oxidized in air at 500oC for various time periods to impart oxide layers of varying thickness. In early 2014, discussions with Indefinite Delivery, Indefinite Quantity (IDIQ) contracted technical consultants from Westinghouse described their previous development (and patents) [R2] on methods of chemical washing to remove some or all of the hydrous oxide layer imparted on UNF cladding during irradiation in light water reactors (LWRs) . Thus, the Oak Ridge National Laboratory (ORNL) study, described herein, was planned to extend the KAERI study on the effects of anhydrous oxide layers, but on larger ~100-gram samples of unirradiated zirconium alloy cladding tubes, and to investigate the effects of various methods of chemical pretreatment prior to chlorination with 100% chlorine on the average reaction rates and Cl2 usage efficiencies.

  2. Geometric Optimization of Hydraulic Rotation Device for Neutron Transmutation Doping

    Energy Technology Data Exchange (ETDEWEB)

    Park, Yongsoo; Kang, Hanok; Park, Kijung; Kim, Seong Hoon; Park, Cheol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The Korea Atomic Energy Research Institute (KAERI) is developing a Hydraulic Rotation Device (HRD) for NTD facilities (NTDHRD) as a part of the Kijang Research Reactor (KJRR) project. This concept has many advantages when compared to the motor driven method, which is currently used in the HANARO research reactor located at KAERI. The OPAL research reactor located at ANSTO has already applied this method. To achieve a constant rotation speed, which is substantial for uniform doping, with a minimal amount of fluid flow, certain geometric requirements should be satisfied. This paper describes the approach we used while determining the number of impulse jet nozzles used to rotate the NTDHRD at a set number of blades as well as the angle of the nozzles of the NTDHRD. The approach that our group has used to geometrically optimize the design of a NTDHRD was described. The adaptation of this approach allows one to predict the required amount of inlet fluid flow and to determine the number of nozzles based on the rule that it should avoid being a divisor of the number of blades, and provides a reference while determining the tile angle of the nozzles. A CFD analysis will be performed as a future study.

  3. Measurement of x-ray energy spectrum by using HPGe detection in 14.5 GHz ECR ion source

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Cheol Ho; Chang, Dae Sik; Oh, Byung Hoon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Seo, Chang Seog; Kim, Yong Kyun [Institute for Basic Science, Daejeon (Korea, Republic of)

    2013-04-15

    The Electron Cyclotron Resonance (ECR) ion source is used to produce intense, high charge state ion beams of intermediate and heavy mass elements. It is widely used to produce ion beams for accelerator, atomic physics research and industrial application. The basic principle of the ECR ion source is the resonance absorption of energy by electron from microwave that has the same frequency as the electron's frequency in the resonance zone. The ECR ion source produces soft and hard x-rays because of efficient heating of electrons. The x-rays are created by electron-ion collisions in the ECR plasma or, when free electrons collide with ECR plasma chamber wall. The generated x-rays are influenced by various input parameters of the ECR ion source. In this study, The x-ray spectrum was measured by using a 14.5 GHz ECR ion source at Korea Atomic Energy Research Institute (KAERI). ECR ion source is used to generate ion beams of heavy mass elements. KAERI has a 14.5 GHz ECR ion source to produce high current ion beam. In this study, experimental condition is provided to generate stable plasma through x-ray spectrum measurement. In the future, x-rays spectra will be measured at various operation conditions such as gas-pressure, trim coil and solenoid current.

  4. Preliminary Assessment of the Interfacial Source Terms in SPACE Code

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Sun Won; Kim, Jeong Woo; Kim, Su Hyong; Kim, Kyung Du [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2009-10-15

    The development program for a nuclear reactor safety analysis code which will be used by utility bodies has been launched supported by the Ministry of Knowledge Economy. The code, named as SPACE, has been designed to solve the multi-dimensional 3-field 2 phase equations. The target power plant type is restricted to PWR's and does not include advanced reactor types, like gas cooled or liquid metal reactors. KAERI, KOPEC, KNF, KEPRI and KHNP are participated in the development project. KAERI has been assigned to develop the physical models and correlations which are required as the closure relationships. The assigned work can be divided into four parts, i.e, (i) the flow regime determination, (ii) the wall heat transfer, (iii) the wall and interfacial friction, and (iv) the interfacial heat and mass transfer. The interfacial heat and mass transfer correlations used in RELAP5, TRAC-M, CATHARE, etc. are reviewed with respect to the simplicity and the range of validity. The recent suggestions are also reviewed. The intellectual property ownerships are proved before an adaptation to the development of the SPACE code. The selected models and correlations are already represented by reference. This paper shows the preliminary assessment results obtained by using the SPACE code.

  5. Geological disposal system development

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Chul Hyung; Kuh, J. E.; Kim, S. K. and others

    2000-04-01

    Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected.

  6. RI and Target recovery system of Lanthanides

    Energy Technology Data Exchange (ETDEWEB)

    Choi, K. H.; Park, U. J.; Jung, S. H.; Kim, J. B.; Moon, J. H.; Nam, S. S.; Jang, K. D. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Separation of adjacent lanthanides is complicated process to obtain pure target nuclide. Several papers have reported that the ionic character change of lanthanides with appropriate chelating agents can isolate the target lanthanides. These specific agents to the metal ion are called as complexing agents including-HIBA, tartaric acid, mandelic acid, lactic acid etc. Radioisotope research division of KAERI has developed separating technique for target lanthanides, total 20mg scale, by using complexing agents and ion-pairing agents in cold state. The reactor-produced radiolanthanides have been pivotal for development of therapeutic radiopharmaceuticals. Some radiolanthanides show excellent theranostic effects in that they have proper Let (Linear Energy Transfer) to induce apoptosis for cancer treatment and gamma ray to use as a tracer for cancer diagnosis. This system was designed for automated separation of the (n,γ) reaction product. Especially, we are focused on getting the carrier free Ho-166 which is the first attempt at KAERI. Even though we have already developed to produce c.a Ho-166(carrier added form), we did not try to develop to produce carrier free Ho-166 since the separating process is difficult as well as production process follows double (n,γ) reaction. After HANARO is re-operated, we are schedule to produce n.c.a Ho by using this recovery system.

  7. A review of neutron scattering correction for the calibration of neutron survey meters using the shadow cone method

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang In; Kim, Bong Hwan; Kim, Jang Lyul; Lee, Jung Il [Health Physics Team, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-12-15

    The calibration methods of neutron-measuring devices such as the neutron survey meter have advantages and disadvantages. To compare the calibration factors obtained by the shadow cone method and semi-empirical method, 10 neutron survey meters of five different types were used in this study. This experiment was performed at the Korea Atomic Energy Research Institute (KAERI; Daejeon, South Korea), and the calibration neutron fields were constructed using a {sup 252}Californium ({sup 252}Cf) neutron source, which was positioned in the center of the neutron irradiation room. The neutron spectra of the calibration neutron fields were measured by a europium-activated lithium iodide scintillator in combination with KAERI's Bonner sphere system. When the shadow cone method was used, 10 single moderator-based survey meters exhibited a smaller calibration factor by as much as 3.1 - 9.3% than that of the semi-empirical method. This finding indicates that neutron survey meters underestimated the scattered neutrons and attenuated neutrons (i.e., the total scatter corrections). This underestimation of the calibration factor was attributed to the fact that single moderator-based survey meters have an under-ambient dose equivalent response in the thermal or thermal-dominant neutron field. As a result, when the shadow cone method is used for a single moderator-based survey meter, an additional correction and the International Organization for Standardization standard 8529-2 for room-scattered neutrons should be considered.

  8. Hydrodynamic Experiments for a Flow Distribution of a 61-pin Wire-wrapped Rod Bundle

    Energy Technology Data Exchange (ETDEWEB)

    Chang, S. K.; Euh, D. J.; Choi, H. S.; Kim, H. M.; Ko, Y. J.; Lee, D. W.; Lee, H. Y.; Choi, S. R. [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    Fuel assembly of the SFR (Sodium-cooled Fast breeder Reactor) type reactor generally has wire spacers which are wrapped around each fuel pin helically in axial direction. The configuration of a helical wire spacer guarantees the fuel rods integrity by providing the bundle rigidity, proper spacing between rods and promoting coolant mixing between subchannels. It is important to understand the flow characteristics in such a triangular array wire wrapped rod bundle in a hexagonal duct. The experimental work has been undertaken to quantify the friction and mixing parameters which characterize the flow distribution in subchannels for the KAERI's own bundle geometric configuration. This work presents the hydrodynamic experimental results for the flow distribution and the pressure drop in subchannels of a 61-pin wire wrapped rod bundle which has been fabricated considering the hydraulic similarity of the reference reactor. Hydrodynamic experiments for a 61-pin wire wrapped test assembly has been performed to provide the data of a flow distribution and pressure losses in subchannels for verifying the analysis capability of subchannel analysis codes for a KAERI's own prototype SFR reactor. Three type of sampling probes have been specially designed to conserve the shape of the flow area for each type of subchannels. All 126 subchannels have been measured to identify the characteristics of the flow distribution in a 37-pin rod assembly. Pressure drops at the interior and the edge subchannels have been also measured to recognize the friction losses of each type of subchannels.

  9. International collaboration on used fuel disposition crystalline rocks

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gardner, Payton [Univ. of Montana, Missoula, MT (United States); Kim, Geon-Young [Korean Atomic Energy Research Inst. Daejeon (Korea); Ji, Sung-Hoon [Korean Atomic Energy Research Inst., Daejeon (Korea)

    2016-08-01

    Active participation in international R&D is crucial for achieving the UFD long-term goals of conducting “experiments to fill data needs and confirm advanced modeling approaches” (by 2015) and of having a “robust modeling and experimental basis for evaluation of multiple disposal system options” (by 2020). DOE’s Office of Nuclear Energy (NE) and its Office of Used Fuel Disposition Research and Development (UFD) have developed a strategic plan to advance cooperation with international partners. The international collaboration on the evaluation of crystalline disposal media at Sandia National Laboratories (SNL) in FY16 focused on the following four activities: (1) thermal-hydrologic-mechanical-chemical modeling single fracture evolution; (2) simulations of flow and transport in Bedrichov Tunnel, Czech Republic, (3) completion of streaming potential testing at Korean Atomic Energy Research Institute (KAERI), and (4) technical data exchange with KAERI on thermal-hydrologic-mechanical (THM) properties and specifications of bentonite buffer materials. The first two activities are part of the Development of Coupled Models and their Validation against Experiments (DECOVALEX-2015) project.

  10. A preliminary economic feasibility assessment of nuclear desalination in Madura Island

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S.-H.; Hwang, Y.-D. [Korea Atomic Energy Research Institute, Yuseong, Daejeon (Korea, Republic of); Konishi, T. [International Atomic Energy Agency, Vienna (Austria); Hudi Hastowo [National Nuclear Energy Agency (BATAN), Jakarta (Indonesia)]. E-mail: hastowo@cbn.net.id

    2005-07-01

    A joint study between KAERI and BATAN, which is entitled 'A preliminary economic feasibility assessment of nuclear desalination in Madura Island', is being conducted under the framework of the Interregional Technical Cooperation Project of IAEA, signed on Oct. 10, 2001 at IAEA. The duration of the project is January 2002 to December 2004. An economic feasibility of nuclear desalination using system-integrated modular advanced reactor (SMART), which will provide Madura Island with electricity and potable water and also support industrialisation and tourism, will be assessed during the project. The scope of this joint study includes the analyses for the short- and long-term energy and water demand as well as the supply plan for Madura Island, evaluation of the site characteristics, environmental impacts and health aspects, technical and economic evaluation of SMART and its desalination system, including the feasibility of its being identified on the Madura Island. KAERI and BATAN are cooperating in conducting a joint study, and IAEA provides technical support and a review of the study products. This paper presents the interim results of the joint study by focussing on the technical and economic aspects of nuclear desalination using SMART in Madura Island. (author)

  11. Development of a Remote Handling System in an Integrated Pyroprocessing Facility

    Directory of Open Access Journals (Sweden)

    Hyo Jik Lee

    2013-10-01

    Full Text Available Over the course of a decade-long research programme, the Korea Atomic Energy Research Institute (KAERI has developed several remote handling systems for use in pyroprocessing research facilities. These systems are now used successfully for the operation and maintenance of processing equipment. The most recent remote handling system is the bridge-transported dual arm servo-manipulator system (BDSM, which is used for remote operation at the world’s largest pyroprocess integrated inactive demonstration facility (PRIDE. Accurate and reliable servo-control is the basic requirement for the BDSM to accomplish any given tasks successfully in a hot- cell environment. To achieve this end, the hardware and software of a digital signal processor-based remote control system were fully custom-developed and implemented to control the BDSM. To reduce the residual vibration of the BDSM, several input profiles, including input shaping, were carefully chosen and evaluated. Furthermore, a time delay controller was employed to achieve good tracking performance and systematic gain tuning. The experimental results demonstrate that the applied control algorithms are more effective than conventional approaches. The BDSM successfully completed its performance tests at a mock-up and was installed at PRIDE for real-world operation. The remote handling system at KAERI is expected to advance the actualization of pyroprocessing.

  12. Stability analysis of the Korean prototype generation-IV sodium-cooled fast reactor using linear frequency domain approach

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Ji; Ha, Pham Nhu Viet; Lim, Jae Yong; Hahn, Do Hee; Kang, Chang Mu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of). Fast Reactor Development Div.

    2016-03-15

    The Korea Atomic Energy Research Institute (KAERI) has been developing the 150 MWe Prototype Generation-IV Sodium-cooled Fast Reactor (PGSFR). The design concept is highly based on passive safety mechanisms, minimizing the need for engineered safety systems. Presently, it is of primary importance to assure the reactor dynamics and stability against small reactivity disturbances under power operating conditions. KAERI has therefore developed the NuSTAB code for stability analysis of the PGSFR. In NuSTAB, the neutron-kinetic and thermal-hydraulic coupling equations are linearized to form the characteristic equation, which is solved as a generalized eigenvalue problem for determining the decay ratio, an indicator of the system stability. In this paper, the stability of the PGSFR was analyzed by applying the point kinetic and spatial kinetic options in the NuSTAB code. System responses to temperature feedbacks including the Doppler effect, thermal expansion, coolant density change, and overall feedback were studied. The results indicate that the initial U and final TRU cores of the PGSFR are both inherently stable thanks to the temperature feedbacks.

  13. The Self-Calibration Test of flowmeter installed in STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) facility

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Minhwan; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The objective of this study is to describe the procedure of the self-calibration test for the flowmeters and to analyze the result of the test. In this work, the test procedure of the self-calibration of two flowmeters (FT-101, FT-102) installed in STELLA facility was described and the test result was analyzed. In regard to the long-term SFR development plan, a large-scale sodium thermal-hydraulic test project is being progressed by KAERI. This project is called STELLA (Sodium Integral Effect Test Loop for Safety Simulation and Assessment), and it is proceeding by adopting the QA (Quality Assurance) program. Due to the specificity of an experiment using sodium(Na) categorized as Class 3(pyrophoric material and water-prohibiting substance) by the Safety Control of Dangerous Substances Act, it is necessary to apply QA in consideration of the sodium experiment environment in certain parts. The one of them is about calibration of measuring instrument such as a flowmeter, thermocouple and pressure gauge. It is described in the QAP (Quality Assurance Procedures) of KAERI that calibration work should be conducted in accordance with self-calibration procedures in a special case where conventional calibration is not practicable. The calibration of two flowmeters (FT-101, FT-102) installed in STELLA facility is the typical example. As a result of test, it was confirmed that the flowmeters meet the pass criterion. Therefore, it was concluded that the flowmeters maintain instrument capacity a year ago.

  14. An Application Example Analysis of Quality Assurance Program for STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) Project

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Minhwan; Gam, Dayoung; Eoh, Jae-Hyuk; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    KAERI has been conducting various basic R and D activities in the field of nuclear technology. In addition, KAERI is now participating in the Generation IV International Forum (GIF), preparing for the development of key technologies for Generation IV nuclear energy system, including Sodium cooled Fast Reactor (SFR) development. All of the key technologies for SFR development need an appropriate level of QA activities to achieve the GIF safety and performance objectives. Therefore, QA activities have been conducted as an essential part of the national SFR project. As a result, QAM (Quality Assurance Manual) and QAP (Quality Assurance Procedures) have been developed for the SFR project, which are based on ASME NQA-1, KEPIC QAP and the GIF Quality Management System Guidelines. In this work, the introduction background and application examples of the QA program for the STELLA project were investigated. Application of the QA for the STELLA project has great significance because the QA has been mainly applied for the nuclear power plant area in operation, which helps ensure the reliability of the test data and completeness of the research performance. Nevertheless, developing more appropriate QA procedures remains a major task because some parts of them are not applicable to the Na-experiment.

  15. Comparative measurement of inorganic elements in Korean space foods using instrumental neutron activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Kim, Sun Ha; Baek, Sung Ryel; Sun, Gwang Min; Moon, Jong Hwa; Choi, Jong Il; Lee, Joo Eun [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    In April 2008, Korea's first astronaut became a crew member of the international space station and she brought special space versions of traditional Korean dishes such as kimchi, boiled rice, hot red pepper paste, soybean paste soup, ginseng tea, green tea, and ramyun. To date, seventy kinds of Korean space foods (KSFs) have been developed by KAERI. The information and role of trace mineral elements from an intake of created and processed foodstuff are important as a indicator of human health and nutrition, as well as a quality control of food and diet. In particular, special food created for consumption by astronauts in outer space may differ with common food on the earth to compensate a decrease in taste and nutrition by hygienic sterilization processing as well as strong cosmic rays, a state of non gravitation, low pressure, and an enclosed space environment. An accurate quantitative analysis of trace elements in various kinds of biological samples is serious work for analytical data quality. An neutron activation analysis is a sensitive, non destructive, multi elemental analytical method without loss and contamination of a sample by chemical pre treatment. The aim of this study is to identify and to compare the distribution of concentrations for essential and functional inorganic elements in six kinds of Korean space foods developed by KAERI in 2011 using INAA.

  16. CFD simulation of turbulent flow in a rod bundle with spacer grids (MATIS-H) using STAR-CCM+

    Energy Technology Data Exchange (ETDEWEB)

    Cinosi, N., E-mail: n.cinosi@imperial.ac.uk; Walker, S.P.; Bluck, M.J.; Issa, R.

    2014-11-15

    Highlights: • CDF simulation of turbulent flow generated by a typical PWR spacer grid. • Benchmarking against the MATIS-H experiments run at KAERI in Daejeon, Korea. • Deployment of various steady RANS models to compute the turbulence. • Sensitivity analysis of hardware components. - Abstract: This paper presents the CFD simulation of the turbulent flow generated by a model PWR spacer grid within a rod bundle. The investigation was part of the MATIS-H benchmark exercise, organized by the OECD-NEA, with measurements performed at the KAERI facilities in Daejeon, Korea. The study employed the CD-Adapco code Star-CCM+. An initial sensitivity study was conducted to attempt to assess the importance to the overall flow of components such as the outlet plenum and the end support grid; these were shown to be able to be safely neglected, but the tapered end portion of the rods was found to be significant, and this was incorporated in the model analyzed. A RANS model using any of K-epsilon, K-omega and Reynolds-stress turbulence models was found to be adequate for the prediction of mean velocity profiles, but they all three underestimate the time-averaged turbulent velocity components. Vorticity seems to be better predicted, although the measured values of vorticity are only presented via colored contour plots, making quantitative comparison rather difficult. Circulation, calculated via an integral for each channel, seems to be well predicted by all three models.

  17. Korea's developmental program for superconductivity

    Science.gov (United States)

    Hong, Gye-Won; Won, Dong-Yeon; Kuk, Il-Hyun; Park, Jong-Chul

    1995-01-01

    Superconductivity research in Korea was firstly carried out in the late 70's by a research group in Seoul National University (SNU), who fabricated a small scale superconducting magnetic energy storage system under the financial support from Korea Electric Power Company (KEPCO). But a few researchers were involved in superconductivity research until the oxide high Tc superconductor was discovered by Bednorz and Mueller. After the discovery of YBaCuO superconductor operating above the boiling point of liquid nitrogen (77 K)(exp 2), Korean Ministry of Science and Technology (MOST) sponsored a special fund for the high Tc superconductivity research to universities and national research institutes by recognizing its importance. Scientists engaged in this project organized 'High Temperature Superconductivity Research Association (HITSRA)' for effective conducting of research. Its major functions are to coordinate research activities on high Tc superconductivity and organize the workshop for active exchange of information. During last seven years the major superconductivity research has been carried out through the coordination of HITSRA. The major parts of the Korea's superconductivity research program were related to high temperature superconductor and only a few groups were carrying out research on conventional superconductor technology, and Korea Atomic Energy Research Institute (KAERI) and Korea Electrotechnology Research Institute (KERI) have led this research. In this talk, the current status and future plans of superconductivity research in Korea will be reviewed based on the results presented in interim meeting of HITSRA, April 1-2, 1994. Taejeon, as well as the research activity of KAERI.

  18. Study on the use of slightly enriched uranium fuel cycle in an existing CANDU 6 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yeom, Choong Sub; Kim, Hyun Dae [Institute for Advanced Engineering, Seoul (Korea, Republic of)

    1997-12-31

    To test the viability of CANFLEX-SEU bundles in an existing CANDU 6 reactor, core follow-up simulation has been carried out using the reactor fueling simulation program of the CANDU 6, RFSP computer code, and a lattice physics code, WIMS-AECL. During the core follow-up, bundle and channel powers and zone levels have been checked against their operating limits at each simulation. It is observed from the simulation results that an equilibrium core loaded with 0.9 w/o CANFLEX-SEU bundles could be refueled and maintained for 550 FPD without any significant violations in the channel and bundle power limits and the permissible operating range of the liquid zone controllers. 8 refs., 2 figs., 1 tab. (Author)

  19. The Impact of Process Scaling on Scratchpad Memory Energy Savings

    Directory of Open Access Journals (Sweden)

    Bennion Redd

    2014-09-01

    Full Text Available Scratchpad memories have been shown to reduce power consumption, but the different characteristics of nanometer scale processes, such as increased leakage power, motivate an examination of how the benefits of these memories change with process scaling. Process and application characteristics affect the amount of energy saved by a scratchpad memory. Increases in leakage as a percentage of total power particularly impact applications that rarely access memory. This study examines how the benefits of scratchpad memories have changed in newer processes, based on the measured performance of the WIMS (Wireless Integrated MicroSystems microcontroller implemented in 180- and 65-nm processes and upon simulations of this microcontroller implemented in a 32-nm process. The results demonstrate that scratchpad memories will continue to improve the power dissipation of many applications, given the leakage anticipated in the foreseeable future.

  20. Analysis constants for database of neutron nuclear data

    Science.gov (United States)

    Bedenko, S. V.; Jeremiah, J. Joseph; Knyshev, V. V.; Shamanin, I. V.

    2016-07-01

    At present there is a variety of experimental and calculation nuclear data which are rather entirely presented in the following evaluated nuclear data libraries: ENDF (USA), JEFF (Europe), JENDL (Japan), TENDL (Russian Federation), ROSFOND (Russian Federation). Libraries of nuclear data, used for neutron-physics calculations in programs: Scale (Origen-Arp), MCNP, WIMS, MCU, and others. Nevertheless all existing nuclear data bases, including evaluated ones, contain practically no information about threshold neutron reactions on 232Th nuclei; available values of outputs and cross-sections significantly differ by orders. The work shows necessity of nuclear constants corrections which are used in the calculations of grids and thorium storage systems. The results of numerical experiments lattices and storage systems with thorium.

  1. Development of a computer code for neutronic calculations of a hexagonal lattice of nuclear reactor using the flux expansion nodal method

    Directory of Open Access Journals (Sweden)

    Mohammadnia Meysam

    2013-01-01

    Full Text Available The flux expansion nodal method is a suitable method for considering nodalization effects in node corners. In this paper we used this method to solve the intra-nodal flux analytically. Then, a computer code, named MA.CODE, was developed using the C# programming language. The code is capable of reactor core calculations for hexagonal geometries in two energy groups and three dimensions. The MA.CODE imports two group constants from the WIMS code and calculates the effective multiplication factor, thermal and fast neutron flux in three dimensions, power density, reactivity, and the power peaking factor of each fuel assembly. Some of the code's merits are low calculation time and a user friendly interface. MA.CODE results showed good agreement with IAEA benchmarks, i. e. AER-FCM-101 and AER-FCM-001.

  2. Visualizing large-scale uncertainty in astrophysical data.

    Science.gov (United States)

    Li, Hongwei; Fu, Chi-Wing; Li, Yinggang; Hanson, Andrew

    2007-01-01

    Visualization of uncertainty or error in astrophysical data is seldom available in simulations of astronomical phenomena, and yet almost all rendered attributes possess some degree of uncertainty due to observational error. Uncertainties associated with spatial location typically vary signicantly with scale and thus introduce further complexity in the interpretation of a given visualization. This paper introduces effective techniques for visualizing uncertainty in large-scale virtual astrophysical environments. Building upon our previous transparently scalable visualization architecture, we develop tools that enhance the perception and comprehension of uncertainty across wide scale ranges. Our methods include a unified color-coding scheme for representing log-scale distances and percentage errors, an ellipsoid model to represent positional uncertainty, an ellipsoid envelope model to expose trajectory uncertainty, and a magic-glass design supporting the selection of ranges of log-scale distance and uncertainty parameters, as well as an overview mode and a scalable WIM tool for exposing the magnitudes of spatial context and uncertainty.

  3. Academic Management and Administration System Reform in Higher Education Institutions

    Institute of Scientific and Technical Information of China (English)

    Xiang Xianming

    2006-01-01

    Reforms in colleges and universities should promote the humanistic character of higher education-rather than simply serve for pure economic production--but also observe the sacred mission of transmiting and creating culture and knowledge.wim these two possessing momentous differences.These then demand rationality in academic management to guard against declination toward dehumanization or bureaucracy.Thus.the relationship between academic power and administrative power must be harmonized,and a reasonable equilibrium must be guaranteed.An academic management idea of power in learning is particularly emphasized to overcome the false polarity of managerism,straightforwardly reducing complicated academic operations to a kind of economic prosecution,hence truly promoting the function of a higher education system.

  4. The genetic basis of amyotrophic lateral sclerosis: recent breakthroughs

    Directory of Open Access Journals (Sweden)

    Eykens C

    2015-10-01

    Full Text Available Caroline Eykens,1,2 Wim Robberecht1–31Research Group Experimental Neurology, Department of Neurosciences, KU Leuven – University of Leuven, Leuven, Belgium; 2Laboratory of Neurobiology, Vesalius Research Center, VIB, Leuven, Belgium; 3Department of Neurology, University Hospitals Leuven, Leuven, BelgiumAbstract: Deciphering the genetic architecture of amyotrophic lateral sclerosis (ALS, an adult-onset neurodegenerative disorder of the motor neuron system, is important to understand the etiology of this fatal disease as well as to develop customized ALS therapies based on the patient's genetic fingerprint. In this review, we discuss the genetic basis of ALS, and attempt to link the causal genes to three highly interrelated pathogenic mechanisms: dysproteostasis, RNA dysregulation, and axon dysfunction. In addition, we address the clinical and biological implications of these genetic findings. Furthermore, we explore to what extent genetic knowledge can be converted into targeted and personalized treatments.Keywords: amyotrophic lateral sclerosis, frontotemporal dementia, genetics, disease modifiers, personalized medicine

  5. Digital Photography and Cinema

    Directory of Open Access Journals (Sweden)

    Alberto Sdegno

    2013-10-01

    Full Text Available In some significant film productions of the last thirty years photography play an innovative role, not only from a technical point of view, but also regarding the plot of the movie. The examples described in the text - from Blade Runner to the recent Inception - may allow a better understanding of the way in which the technology of image processing has altered the perception of film sequences, also helping to transform the opinions on this new way of work by artists usually adopting traditional practices, such as Wim Wenders. His film, Until the end of the world, in fact, appears as an episode particularly eloquent in the filmography of the artist, which testifies a change in the definition of the working method.

  6. Direct Localization Algorithm of White-light Interferogram Center Based on the Weighted Integral Method

    Science.gov (United States)

    Sato, Seichi; Kurihara, Toru; Ando, Shigeru

    This paper proposes an exact direct method to determine all parameters including an envelope peak of the white-light interferogram. A novel mathematical technique, the weighted integral method (WIM), is applied that starts from the characteristic differential equation of the target signal, interferogram in this paper, to obtain the algebraic relation among the finite-interval weighted integrals (observations) of the signal and the waveform parameters (unknowns). We implemented this method using FFT and examined through various numerical simulations. The results show the method is able to localize the envelope peak very accurately even if it is not included in the observed interval. The performance comparisons reveal the superiority of the proposed algorithm over conventional algorithms in all terms of accuracy, efficiency, and estimation range.

  7. The systems of automatic weight control of vehicles in the road and rail transport in Poland

    Directory of Open Access Journals (Sweden)

    2011-09-01

    Full Text Available . Condition of roads in Poland, despite the on-going modernisation works is still unsatisfactory. One reason is the excessive wear caused by overloaded vehicles. This problem also applies to rail transport, although to a much lesser extent. One solution may be the system of automatic weight control of road and rail vehicles. The article describes the legal and organizational conditions of oversize vehicles inspection in Poland. Characterized current practices weighing road vehicles, based on measurements of static technology. The article includes the description of the existing applications of the automatic dynamic weighing technology, known as systems WIM (Weigh in Motion. Additionally, the weighing technology and construction of weighing stands in road and rail are characterized. The article ends with authors' conclusions indicating the direction and ways of improving the weighing control systems for vehicles.

  8. Improving the model of emission from spinning dust: effects of grain wobbling and transient spin-up

    CERN Document Server

    Hoang, Thiem; Lazarian, A

    2010-01-01

    Observations continue to support the interpretation of the anomalous microwave foreground as electric dipole radiation from spinning dust grains as proposed by Draine and Lazarian (1998ab). In this paper we present a refinement of the original model by improving the treatment of a number of physical effects. First, we consider a disk-like grain rotating with angular velocity at an arbitrary angle with respect to the grain symmetry axis and derive the rotational damping and excitation coefficients arising from infrared emission, plasma-grain interactions and electric dipole emission. The angular velocity distribution and the electric dipole emission spectrum for grains is calculated using the Langevin equation, for cases both with and without fast internal relaxation. Our results show that, the peak emissivity of spinning dust, compared to earlier studies, increases by a factor of ~2 for the Warm Neutral Medium (WNM), the Warm Ionized Medium (WIM), the Cold Neutral Medium (CNM) and the Photodissociation Region...

  9. 《皮娜》:致敬灵魂的舞者

    Institute of Scientific and Technical Information of China (English)

    桂清萍

    2013-01-01

    德国著名导演维姆·文德斯(Wim Wenders)在第一次观看皮娜·鲍什(Pina Bausch)出演《穆勒咖啡馆》时,便深深为这位"德国现代舞第一夫人"所吸引。他与皮娜迅速成为至交,并诞生了合作电影的想法。几经考虑,文德斯决定采用3D电影技术来展现皮娜充满激情与创意的现代舞艺术,试图为

  10. 新写实电影先锋--黄建新

    Institute of Scientific and Technical Information of China (English)

    黄欣

    2004-01-01

    @@ 作为多年的影迷,却一直都没能培养起对所谓商业大片的兴趣.大约是因为自己有点小众趣味吧,一直以来都对黑色电影(Film Noir)和独立制作(Independence Making)情有独钟,我的影碟收藏基本上都是艺术片,大部分是来自欧洲的作品,像法斯宾德(Rainer Werner Fassbinder)、博格曼(Ingmar Bergman)、文德斯(Wim Wenders)、费里尼(Federico Fellini)等等.

  11. Estimation of Control Rod Worth in a VVER-1000 Reactor using DRAGON4 and DONJON4

    Directory of Open Access Journals (Sweden)

    Saadatian-derakhshandeh Farahnaz

    2014-07-01

    Full Text Available One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors. In this paper, we developed a justifiable approach called D4D4 to estimate the control rod worth of a VVER-1000 reactor that enables to perform the best estimate analysis and reduce the conservatism that utilize DRAGON4 and DONJON4. The results are compared with WIMS-D4/CITATION to show the effectiveness and superiority of the developed package in predicting reactivity worth of the rod and also other reactor physics parameters of the VVER-1000 reactor. The results of this study are in good agreement with the plant's FSAR.

  12. News from the Library: E-book or printed book? You can have the best of both worlds!

    CERN Multimedia

    CERN Library

    2011-01-01

    Over the last couple of years, the Library has been expanding its collection of electronic books. The most popular titles are, of course, also bought as paper copies and are available for loan.   More than 15,000 titles, across all CERN-relevant disciplines, are now available for download from the Library. Recently, Springer physics and astronomy books, as well as all volumes from Lecture Notes in Physics, were added. So, from now on, readers will not have to queue up for popular books such as "Particle Accelerator Physics" (Wiedemann) or "Particle Detection with Drift Chambers" (Blum, Rolandi and Riegler), which are often in high demand. From left to right: Tullio Basaglia (CERN Library), Christian Caron (Springer) and Wim van der Stelt (Springer). In addition to providing electronic access, the publisher offers people at CERN the possibility to purchase paperback copies, distributed under the label “My Copy”, for the tempting price of &a...

  13. Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes

    Directory of Open Access Journals (Sweden)

    Lindley Benjamin A.

    2016-01-01

    Full Text Available The majority of nuclear reactors operating in the world today and similarly the majority of near-term new build reactors will be LWRs. These currently accommodate traditional Zr clad UO2/PuO2 fuel designs which have an excellent performance record for normal operation. However, the events at Fukushima culminated in significant hydrogen production and hydrogen explosions, resulting from high temperature Zr/steam interaction following core uncovering for an extended period. These events have resulted in increased emphasis towards developing more accident tolerant fuels (ATFs-clad systems, particularly for current and near-term build LWRs. R&D programmes are underway in the US and elsewhere to develop ATFs and the UK is engaging in these international programmes. Candidate advanced fuel materials include uranium nitride (UN and uranium silicide (U3Si2. Candidate cladding materials include advanced stainless steel (FeCrAl and silicon carbide. The UK has a long history in industrial fuel manufacture and fabrication for a wide range of reactor systems including LWRs. This is supported by a national infrastructure to perform experimental and theoretical R&D in fuel performance, fuel transient behaviour and reactor physics. In this paper, an analysis of the Integral Inherently Safe LWR design (I2S-LWR, a reactor concept developed by an international collaboration led by the Georgia Institute of Technology, within a US DOE Nuclear Energy University Program (NEUP Integrated Research Project (IRP is considered. The analysis is performed using the ANSWERS reactor physics code WIMS and the EDF Energy core simulator PANTHER by researchers at the University of Cambridge. The I2S-LWR is an advanced 2850 MWt integral PWR with inherent safety features. In order to enhance the safety features, the baseline fuel and cladding materials that were chosen for the I2S-LWR design are U3Si2 and advanced stainless steel respectively. In addition, the I2S-LWR design

  14. Clock-turning gait synthesis for humanoid robots

    Institute of Scientific and Technical Information of China (English)

    Zhe TANG; Zengqi SUN; Hongbo LIU; Meng Joo ER

    2007-01-01

    Turning gait is a basic motion for humanoid robots.This paper presents a method for humanoid turning.i.e.clock-turning.The objective of clock-turning is to change robot direction at a stationary spot.The clock-turning planning consists of four steps:ankle trajectory generation,hip trajectory generation,knee trajectory generation,and inverse kinematics calculation.Our proposed method is based on a typical humanoid structure with 12 DOFs(degrees of freedom).The final output of clock-turning planning is 12 reference trajectories.which are used to control a humanoid robot wim 12 DOFs.ZMP(zero moment point)is used as stability criterion for the planning.Simulation experiments are conducted to verify the effectiveness of our proposed clock-turning method.

  15. Burn-up credit in criticality safety of PWR spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Mahmoud, Rowayda F., E-mail: Rowayda_mahmoud@yahoo.com [Metallurgy Department, Nuclear Research Center, Atomic Energy Authority (Egypt); Shaat, Mohamed K. [Nuclear Engineering, Reactors Department, Nuclear Research Center, Atomic Energy Authority (Egypt); Nagy, M.E.; Agamy, S.A. [Professor of Nuclear Engineering, Nuclear and Radiation Department, Alexandria University (Egypt); Abdelrahman, Adel A. [Metallurgy Department, Nuclear Research Center, Atomic Energy Authority (Egypt)

    2014-12-15

    Highlights: • Designing spent fuel wet storage using WIMS-5D and MCNP-5 code. • Studying fresh and burned fuel with/out absorber like “B{sub 4}C and Ag–In–Cd” in racks. • Sub-criticality was confirmed for fresh and burned fuel under specific cases. • Studies for BU credit recommend increasing fuel burn-up to 60.0 GWD/MTU. • Those studies require new core structure materials, fuel composition and cladding. - Abstract: The criticality safety calculations were performed for a proposed design of a wet spent fuel storage pool. This pool will be used for the storage of spent fuel discharged from a typical pressurized water reactor (PWR). The mathematical model based on the international validated codes, WIMS-5 and MCNP-5 were used for calculating the effective multiplication factor, k{sub eff}, for the spent fuel stored in the pool. The data library for the multi-group neutron microscopic cross-sections was used for the cell calculations. The k{sub eff} was calculated for several changes in water density, water level, assembly pitch and burn-up with different initial fuel enrichment and new types and amounts of fixed absorbers. Also, k{sub eff} was calculated for the conservative fresh fuel case. The results of the calculations confirmed that the effective multiplication factor for the spent fuel storage is sub-critical for all normal and abnormal states. The future strategy for the burn-up credit recommends increasing the fuel burn-up to a value >60.0 GWD/MTU, which requires new fuel composition and new fuel cladding material with the assessment of the effects of negative reactivity build up.

  16. HERSCHEL GALACTIC PLANE SURVEY OF [N ii] FINE STRUCTURE EMISSION

    Energy Technology Data Exchange (ETDEWEB)

    Goldsmith, Paul F.; Yıldız, Umut A.; Langer, William D.; Pineda, Jorge L., E-mail: Paul.F.Goldsmith@jpl.nasa.gov [Jet Propulsion Laboratory, California Institute of Technology, 4800 Oak Grove Drive, Pasadena, CA 91109 (United States)

    2015-12-01

    We present the first large-scale high angular resolution survey of ionized nitrogen in the Galactic Plane through emission of its two fine structure transitions ([N ii]) at 122 and 205 μm. The observations were largely obtained with the PACS instrument onboard the Herschel Space Observatory. The lines of sight were in the Galactic plane, following those of the Herschel OTKP project GOT C+. Both lines are reliably detected at the 10{sup −8}–10{sup −7} Wm{sup −2} sr{sup −1} level over the range –60° ≤ l ≤ 60°. The rms of the intensity among the 25 PACS spaxels of a given pointing is typically less than one third of the mean intensity, showing that the emission is extended. [N ii] is produced in gas in which hydrogen is ionized, and collisional excitation is by electrons. The ratio of the two fine structure transitions provides a direct measurement of the electron density, yielding n(e) largely in the range 10–50 cm{sup −3} with an average value of 29 cm{sup −3} and N{sup +} column densities 10{sup 16}–10{sup 17} cm{sup −2}. [N ii] emission is highly correlated with that of [C ii], and we calculate that between 1/3 and 1/2 of the [C ii] emission is associated with the ionized gas. The relatively high electron densities indicate that the source of the [N ii] emission is not the warm ionized medium (WIM), which has electron densities more than 100 times smaller. Possible origins of the observed [N ii] include the ionized surfaces of dense atomic and molecular clouds, the extended low-density envelopes of H ii regions, and low-filling factor high-density fluctuations of the WIM.

  17. Using weigh-in-motion data to determine bridge dynamic amplification factor

    Directory of Open Access Journals (Sweden)

    Kalin Jan

    2015-01-01

    Full Text Available The dynamic component of bridge traffic loading is commonly taken into account with a Dynamic Amplification Factor (DAF – the ratio between the maximum dynamic and static load effects on a bridge. In the design codes, this factor is generally higher than in reality. While this is fine for new bridges that must account for various risks during their life-time, it imposes unnecessary conservativism into assessment of the existing well defined bridges. Therefore, analysis of existing bridges should apply more realistic DAF values. One way of obtaining them experimentally is by bridge weigh-in-motion (B-WIM measurements, which use an existing instrumented bridge or culvert to weigh all crossing vehicles at highway speeds. The B-WIM system had been equipped with two methods of obtaining an approximation to the static response of the. The first method uses the sum of influence lines. This method relies on accurate axle identification, the failure of which can have a large influence on the DAF value. The other method uses a pre-determined low-pass filter to remove the dynamic component of the measured signal; however an expert is needed to set the filter parameters. A new approach that tries to eliminate these two drawbacks has been developed. In this approach the parameters for the filter are determined automatically by fitting the filtered response to the sum of the influence lines. The measurement of DAF on a typical bridge site agrees with experiments performed in the ARCHES [1] project: dynamic amplification decreases as static loading increases.

  18. '05 Safety Case in a Potential HLW Disposal in ROK for Better Communication among Stakeholders

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Y.S. [Korea Atomic Energy Research Inst., Daejeon (Korea)

    2006-09-15

    The national effort to secure a site to dispose of LLW In Korea has been successfully completed when Gyeongjoo was finally selected through its local referendum on Nov 2 in 2005. The focus has been shifted to the future of spent nuclear fuels generated by 20 reactors in four nuclear complexes. Korea has a solid plan to raise its nuclear share, with 28 reactors in operation, in the electricity generation to 46.7% by 2017.The total amount of spent nuclear fuel from these reactors will be 36,000 MT. To dispose of 36,000 MT, at least a four square kilometer underground layer is required. The characteristics of Korean disposal conditions are rather unique. Korea has a mixture of CANDU and PWR whose inventories and decay heats are quits different. The spent nuclear fuel is assumed to be emplaced into stainless steel containers filled with cast iron. Calcium bentonite is used as a buffer material between a waste container and a surrounding rock. Radionuclides passing through barriers will eventually reach the biosphere. Two pathways are identified as major ones; one following the stream of ground and surface waters to the ground surface, a river and a marine environment, the other intersecting a small well whose extracted water is consumed by local residents. To safely dispose of spent nuclear fuels KAERI has developed the Korean Reference Disposal System (KRS). To assess the long term post closure radiological safety, KAERI has developed the following products: (1) The KAERI FEP Encyclopedia; (2) Reference and alternative scenarios in association with the corresponding rock engineering system matrices, assessment method context and flow charts; (3) Assessment codes MASCOT-K and MDPSA; (4) PAID, the input datahabe for total system performance assessment; (5) Safety assessment on two reference and other selected scenarios; (6) Korean biosphere modeling. and (7) Quality assurance systems in association with the CYPRUS, the cyber RandD platform system; and (8) The flow

  19. Preparation of Teflon pellets use of CaSO{sub 4}:Dy TL Material and Study of TL Characteristics

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Jeong Sun

    2000-02-15

    As the handling of radioactive materials is frequent, radiation protection which can be achieved through accurate measurements of the radiation exposure doses is of primary concern to the workers involved. Several types of dosimeters, such as the thermoluminescent dosimeter(TLD), film badge and pocket dosimeter, have been used to monitor personal exposure doses. Among these, TLD has been generally accepted as the most accurate and reliable method of personal dosimetry, because of its superior and long term stability. All of the TLDs currently used in Korea have been imported from abroad, Korea Atomic Energy Research Institute(KAERI) is now developing new types of TLD which has more sensitivity and stability. One of the thermoluminescent material KAERI is presently investigating is CaSO{sub 4}:Dy, in which a small concentration of Dy is added as activator. This thesis presents a method of preparing the CaSO{sub 4}:Dy phosphor-embeded teflon powder which is then compressed to thin pellet form used as the TLD element. Investigations are made to determine optimum preparing conditions which are resulted the largest emission of the thermoluminescence. Also experimental investigations are conducted for the characteristics of the CaSO{sub 4}:Dy Teflon pellet such as the energy response, dose response, reusability, sensitivity, lowest level of detection, and fading. The optimum preparing conditions have been found as: the concentration of activator Dy is 0.1 mol%: the disolved temperature of Dy is 320 .deg. C: the sintering temperature of the CaSO{sub 4}:Dy phosphor is 750 .deg. C for 2 hours: the average grain sizes of the CaSO{sub 4}:Dy phosphor are 100-200{mu}m. Our investigation shows that the sensitivity of the CaSO{sub 4}:Dy pellet is 1.25-time higher than that of the commercial Teledyne CaSO{sub 4}:Dy pellet. A dose response is observed to linear in the range of 10{sup 4} to 10 Gy. The relative energy response(RER) in the low energy region is 9.6(for the {sup 137}Cs

  20. The development of uranium foil farication technology utilizing twin roll method for Mo-99 irradiation target

    CERN Document Server

    Kim, C K; Park, H D

    2002-01-01

    MDS Nordion in Canada, occupying about 75% of global supply of Mo-99 isotope, has provided the irradiation target of Mo-99 using the rod-type UAl sub x alloys with HEU(High Enrichment Uranium). ANL (Argonne National Laboratory) through co-operation with BATAN in Indonesia, leading RERTR (Reduced Enrichment for Research and Test Reactors) program substantially for nuclear non-proliferation, has designed and fabricated the annular cylinder of uranium targets, and successfully performed irradiation test, in order to develop the fabrication technology of fission Mo-99 using LEU(Low Enrichment Uranium). As the uranium foils could be fabricated in laboratory scale, not in commercialized scale by hot rolling method due to significant problems in foil quality, productivity and economic efficiency, attention has shifted to the development of new technology. Under these circumstances, the invention of uranium foil fabrication technology utilizing twin-roll casting method in KAERI is found to be able to fabricate LEU or...

  1. A study on the research and development planning of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Byong Chull; Won, B. C.; Kim, J. W.; Cho, C. Y.; Cheon, S. H.; Kim, J. U.; Kim, I. C.; Hong, Y. P.; Kang, W. J.; Lee, H. S.; Yoon, Y. S.; Park, J. H.; Kim, S. S.; Park, C. S.; Yang, M. S.; Lee, Y. H

    1998-01-01

    This study was performed aiming to provide the basic input to establish `the mild and long-term nuclear R and D program (1997 - 2006)` for government. This program is announced by the government as an official plan after endorsement of Atomic Energy Commission (AEC). Second, the historical formation and transition of both nuclear R and D policy and nuclear R and D development system after the introduction of nuclear energy in Korea were analyzed. Third, the current status of several nuclear-related R and D projects and R and D management, which have been conducted at KAERI were analyzed and a better direction for effective and efficient R and D activities was suggested. Finally, on the basis of above analysis, this study made an effort to extract the appropriate lessons for future directions for carrying out nuclear R and D projects. (author). 19 refs., 40 tabs., 10 figs

  2. Treatment of Decommissioning Combustible Wastes with Incineration Technology

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. Y. Min; Yang, D. S.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The aim of the paper is current status of management for the decommissioning radioactive combustible and metal waste in KAERI. In Korea, two decommissioning projects were carried out for nuclear research facilities (KRR-1 and KRR-2) and a uranium conversion plant (UCP). Through the two decommissioning projects, lots of decommissioning wastes were generated. Decommissioning waste can be divided into radioactive waste and releasable waste. The negative pressure of the incineration chamber remained constant within the specified range. Off-gas flow and temperature were maintained constant or within the desired range. The measures gases and particulate materials in the stack were considerably below the regulatory limits. The achieved average volume reduction ratio during facility operation is about 1/65.

  3. Validation of new {sup 240}Pu cross section and covariance data via criticality calculation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Do Heon; Gil, Choong-Sup; Kim, Hyeong Il; Lee, Young-Ouk, E-mail: kimdh@kaeri.re.kr, E-mail: csgil@kaeri.re.kr, E-mail: hikim@kaeri.re.kr, E-mail: yolee@kaeri.re.kr [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Leal, Luiz C.; Dunn, Michael E., E-mail: leallc@ornl.gov, E-mail: dunnme@ornl.gov [Oak Ridge National Laboratory, TN (United States)

    2011-07-01

    Recent collaboration between KAERI and ORNL has completed an evaluation for {sup 240}Pu neutron cross section with covariance data. The new {sup 240}Pu cross section data has been validated through 28 criticality safety benchmark problems taken from the ICSBEP and/or CSEWG specifications with MCNP calculations. The calculation results based on the new evaluation have been compared with those based on recent evaluations such as ENDF/B-VII.0, JEFF-3.1.1, and JENDL-4.0. In addition, the new {sup 240}Pu covariance data has been tested for some criticality benchmarks via the DANTSYS/SUSD3D-based nuclear data sensitivity and uncertainty analysis of k{sub eff}. The k{sub eff} uncertainty estimates by the new covariance data has been compared with those by JENDL-4.0, JENDL-3.3, and Low-Fidelity covariance data. (author)

  4. The Results of the Second NACEF Test

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong-Hwan; Bae, Yoon-Yeong; Kim, Chan-Soo; Hong, Sung-Deok; Kim, Eung-Seon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    RCCS (Reactor Cavity Cooling System) is the only ex-vessel passive safety system that will ensure the safety of the PMR200, and its performance needs to be verified. For the difficulty of the fullscale test, a 1/4-scale RCCS facility, NACEF, was constructed at KAERI and a few tests have satisfactorily been performed. Here described are the results of the second main test which aimed at the evaluation of heat transfer with the scaled air velocity in the risers and the scaled air temperature increment during passing through the risers. The second main test was performed in the NACEF facility, the 1/4-scale RCCS mockup of PMR200. Natural convection cooling by buoyant force formed in the risers for a scaled condition. The RCCS in the prototypic PMR200 is expected to perform well. The heat transfer regime is in between the mixed convection and the forced convection.

  5. Metallic Reactor Fuel Fabrication for SFR

    Energy Technology Data Exchange (ETDEWEB)

    Song, Hoon; Kim, Jong-Hwan; Ko, Young-Mo; Woo, Yoon-Myung; Kim, Ki-Hwan; Lee, Chan-Bock [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The metal fuel for an SFR has such advantages such as simple fabrication procedures, good neutron economy, high thermal conductivity, excellent compatibility with a Na coolant, and inherent passive safety 1. U-Zr metal fuel for SFR is now being developed by KAERI as a national R and D program of Korea. The fabrication technology of metal fuel for SFR has been under development in Korea as a national nuclear R and D program since 2007. The fabrication process for SFR fuel is composed of (1) fuel slug casting, (2) loading and fabrication of the fuel rods, and (3) fabrication of the final fuel assemblies. Fuel slug casting is the dominant source of fuel losses and recycled streams in this fabrication process. Fabrication on the rod type metallic fuel was carried out for the purpose of establishing a practical fabrication method. Rod-type fuel slugs were fabricated by injection casting. Metallic fuel slugs fabricated showed a general appearance was smooth.

  6. Study on the AMO data production and processing techniques

    Energy Technology Data Exchange (ETDEWEB)

    Rhee, Yong Joo; Yoo, B. D.; Choe, A. S.; Han, J. M.; Jung, E. C.; Rho, S. P.; Yi, J. H.; Jeong, D. Y.; Lee, K. S.; Park, H. M.; Kim, S. K.; Song, K. S.; Lee, J. M.

    1996-01-01

    A computer system has been established with a DEC Alphastation 600 with 12.9 GB storage capacity and UNIX O/S for an AMO database system. CERN 3.0 WWW server program has been installed in this system and AMO bibliographic data ( larger than 55 MB in size) has been implemented. These data are the ones of atomic energy levels and transition probabilities derived from the NIST database system, which contain about 1400 references of energy levels and about 5000 references of transition probabilities. Also from the NIFS of Japan, more than 150 booklets of data report have been obtained with the favor of NIFS to provide KAERI with their data reports related to the AMO data. Meanwhile a spectroscopic parameter of Sm which is one of the rate earth elements, has been measured, resulting in production of 36 isotope shift data of the high-lying even parity states. (author). 14 refs., 5 tabs., 4 figs.

  7. Report on preliminary analysis of state of nuclear criticality accident at JCO at Tokaimura, Ibaraki, Japan (I)

    Energy Technology Data Exchange (ETDEWEB)

    Ha, J.J.; Park, J.H.; Chang, J.H. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-10-01

    This preliminary report was prepared by the Special Task Force Team of KAERI in order to analysis status of nuclear criticality accident broken out at 10:35 September 30, 1999 at JCO nuclear conversion test facility located at Tokaimura, Ibaraki, Japan. The report was consisted of accident summary of cause of accident summary of cause of accident and response by relevant organizations, and preliminary technical analysis of radiation exposure of JCO workers, analysis of cause of accident, and accident assessment and preventive actions against criticality accident. It is expected that JCO accident, Japan's first nuclear criticality accident, would make significant effects to Japan nuclear policy and would be also a good example to Korea future actions to be taken in use and development of nuclear energy. 63 refs., 3 figs., 1 tab. (Author)

  8. Pressure loss tests for DR-BEP of fullsize 17 x 17 PWR fuel assembly

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Moon Ki; Chun, Se Young; Chang, Seok Kyu; Won, Soon Youn; Cho, Young Rho; Kim, Bok Deuk; Min, Kyoung Ho [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-01-01

    This report describes the conditions, procedure and results in the pressure loss tests carried out for a double grid type debris resistance bottom end piece (DR-BEP) designed by KAERI. In this test, the pressure loss coefficients of the full size 17 x 17 PWR simulated fuel assembly with DR-BET and with standard-BEP were measured respectively, and the pressure loss coefficients of DR-BEP were compared with the coefficients of STD-BET. The test conditions fall within the ranges of loop pressure from 5.2 to 45 bar, loop temperature from 27 to 221 deg C and Reynolds number in fuel bundle from 2.17 x 10{sup 4} to 3.85 x 10{sup 5}. (Author) 5 refs., 18 figs., 5 tabs.

  9. Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank

    Directory of Open Access Journals (Sweden)

    Hyoung Tae Kim

    2015-01-01

    Full Text Available In order to simulate the CANDU-6 moderator circulation phenomena during steady state operating and accident conditions, a scaled-down moderator test facility has been constructed at Korea Atomic Energy Institute (KAERI. In the present work an experiment using a 1/40 scaled-down moderator tank has been performed to identify the potential problems of the flow visualization and measurement in the scaled-down moderator test facility. With a transparent moderator tank model, a flow field is visualized with a particle image velocimetry (PIV technique under an isothermal state, and the temperature field is measured using a laser induced fluorescence (LIF technique. A preliminary CFD analysis is also performed to find out the flow, thermal, and heating boundary conditions with which the various flow patterns expected in the prototype CANDU-6 moderator tank can be reproduced in the experiment.

  10. Scaled-Down Moderator Circulation Test Facility at Korea Atomic Energy Research Institute

    Directory of Open Access Journals (Sweden)

    Hyoung Tae Kim

    2016-01-01

    Full Text Available Korea Atomic Energy Research Institute (KAERI started the experimental research on moderator circulation as one of a the national research and development programs from 2012. This research program includes the construction of the moderator circulation test (MCT facility, production of the validation data for self-reliant computational fluid dynamics (CFD tools, and development of optical measurement system using the particle image velocimetry (PIV. In the present paper we introduce the scaling analysis performed to extend the scaling criteria suitable for reproducing thermal-hydraulic phenomena in a scaled-down CANDU- (CANada Deuterium Uranium- 6 moderator tank, a manufacturing status of the 1/4 scale moderator tank. Also, preliminary CFD analysis results for the full-size and scaled-down moderator tanks are carried out to check whether the moderator flow and temperature patterns of both the full-size reactor and scaled-down facility are identical.

  11. Evaluation of TASS/SMR with steady state analysis of high temperature/high pressure thermal-hydraulic test facility (VISTA)

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Dong Ju; Choi, Yong Won; Park, Chang Hwan; Lee, Un Chul [Seoul National University, Seoul (Korea, Republic of); Hwang, Young Dong; Lee, Kyu Hyung; Kim, Hee Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    The TASS/SMR code is the revised version of the TASS code, which is the result of code development effort of KAERI since 1997, for safety analysis of NPP coolant system. Lately, it is scheduled to evaluate thermal-hydraulic phenomena during several transient periods of SMART-P with TASS/SMR. To establish the pertinence of the calculative results of TASS/SMR, there should be a process of validation and verification of TASS/SMR. The objective of this study is validating the numerical capability and reliability of TASS/SMR with steady state analysis of VISTA (Experimental Verification by Integral Simulation of Transient and Accidents) that was designed to simulate SMART-P.

  12. Status of Beam Diagnostic Systems for the PEFP

    CERN Document Server

    Park Jang Ho; Choi Byung Ho; Ha Hwang Woon; Han, Sang-Hyo; Park, Sung-Ju; Woon Parc, Yong; Yun Huang Jung

    2005-01-01

    A proton linear accelerator is currently the construction at the KAERI (Korea Atomic Research Institute) to the PEFP (Proton Engineering Frontier Project) in Korea. We are accomplished the technique development of beam diagnostic system to be currently the construction. We treat beam diagnostics for the high power proton linear accelerator. Prototype beam position & phase monitor (BPPM) electronics was made and tested successfully in one of the beam diagnostic systems. The beam position monitor pickup electrode is a capacitive type (electrostatic type) which has a button form. Button form electrode, in common use around electron synchrotrons and storage rings, are a variant of the electrode with small button form (e.g., sub mm diameter). However, we are designed button form electrode to measure beam position of proton beam. The BCM (Beam Current Monitor) is developed Tuned CT (Current Transformer) for collaborate with Bergoz Instruments. This paper describes the status of beam diagnostic systems for the P...

  13. Development of objective provision trees for Sodium-Cooled Fast Reactor Defense-in-depth evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Huichang [TUEV Rheinland Korea Ltd., Seoul (Korea, Republic of); Suh, Namduk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-05-15

    KALIMER is one of sodium-cooled fast reactor and being developed by Korea Atomic Energy Research Institute (KAERI), was developed and suggested in this paper. Developed OPT is for the defense-in-depth level 3, core heat removal safety function. Using OPT method, the evaluation of defense-in-depth implementation for the design features of KALIMER reactors were tried in this study. To utilize the design information of KALIMER, challenges in OPTs which are under development in this study, were identified based on the system physical boundaries. This approach make the identification of possible and postulated challenges much clear and this will be a benefit to further identification of provisions in KALIMER design. OPTs for other levels of defense-in-depth and other safety functions are under development.

  14. Evaluation of the measurement geometries and data processing algorithms for industrial gamma tomography technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, N.Y. [Radioisotope Research Division, Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon 305-353 (Korea, Republic of)], E-mail: nayoung4493@gmail.com; Jung, S.H. [Radioisotope Research Division, Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon 305-353 (Korea, Republic of)], E-mail: shjung3@kaeri.re.kr; Kim, J.B. [Radioisotope Research Division, Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon 305-353 (Korea, Republic of)], E-mail: jong@kaeri.re.kr

    2009-07-15

    In this paper, we evaluated the measurement geometries and data processing algorithms for industrial gamma tomography technology. Several phantoms simulating industrial objects were tested in various conditions with the gamma-ray CT system developed in KAERI (Korea Atomic Energy Research Institute). Radiation was measured with lead shielded 24 1x1 in Nal detectors. Regarding the parallel beam geometry, the EM algorithm showed the best resolution among the algebraic reconstruction technique (ART), simultaneous iterative reconstructive technique (SIRT) and expectation maximization (EM). However, the fan beam scanning was more time efficient than the parallel projection for the similar quality of reconstructed image. Future developments of the industrial gamma ray CT will be focused on a large-scale application which is more practical for a diagnosis in the petrochemical industry.

  15. Post irradiation test report of irradiated DUPIC simulated fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Myung Seung; Jung, I. H.; Moon, J. S. and others

    2001-12-01

    The post-irradiation examination of irradiated DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors) simulated fuel in HANARO was performed at IMEF (Irradiated Material Examination Facility) in KAERI during 6 months from October 1999 to March 2000. The objectives of this post-irradiation test are i) the integrity of the capsule to be used for DUPIC fuel, ii) ensuring the irradiation requirements of DUPIC fuel at HANARO, iii) performance verification in-core behavior at HANARO of DUPIC simulated fuel, iv) establishing and improvement the data base for DUPIC fuel performance verification codes, and v) establishing the irradiation procedure in HANARO for DUPIC fuel. The post-irradiation examination performed are {gamma}-scanning, profilometry, density, hardness, observation the microstructure and fission product distribution by optical microscope and electron probe microanalyser (EPMA)

  16. Korean contribution to the IAEA coordinated research programme (CRP-IV) on assuring structural integrity of PRV's (II)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Bong Sang; Hong, J.H.; Byun, T.S.; Kim, J.H.; Yang, W.J

    1998-11-01

    This report summarize the results obtained from the second year contribution of KAERI to the IAEA CRP-IV on Assuring Structural Integrity of Reactor Pressure Vessels. The mandatory part of this programme is to perform fracture toughness (K{sub JC}) tests using pre-cracked Charpy specimens on the IAEA reference material JRQ (ASTM A533-B1 steel). The results will be used to validate the small specimens for surveillance tests. In this report, three different heats of reactor pressure vessel materials are characterized by the ASTM E 1921-97 Standard Test Method for Determination of Reference Temperature, T{sub 0}, for Ferritic Steels in the TRansition Range. The materials are the IAEA reference plate (JRQ), a Japanese forging (JFL), and a Korean forging (KFY5). A special emphasis is focused on the loading rate effect and the limit of the validity range for T{sub 0} determination. (author). 5 refs., 5 tabs., 16 figs.

  17. Fracture toughness evaluation using small specimens for assuring structural integrity of PRV's

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Bong Sang; Hong, J. H.; Chi, S. H.; Kim, J. H.; Yang, W. J

    1999-08-01

    This report summarizes the results obtained from the three year contribution of KAERI to the IAEA-CRP on ''Assuring Structural Integrity of Reactor Pressure Vessels''. The mandatory part of this programme is to perform fracture toughness K{sub jc} tests using pre-cracked Charpy specimens on the IAEA reference material JRQ (ASTM A533-B1 steel). The results will be used to validate the small specimens for surveillance tests. In this report, three different heats of reactor pressure vessel materials are characterized by the ASTM E 1921-97 'standard test method for determination of reference temperature, T{sub o}, for ferritic steels in the transition range'. The materials are the IAEA reference plate (JRQ), a Japanese forging (JEL), and a Korean forging (KFY5). 6 refs., 7 tabs., 20 figs.

  18. Passive heat removal characteristics of SMART

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Jae Kwang; Kang, Hyung Seok; Yoon, Joo Hyun; Kim, Hwan Yeol; Cho, Bong Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    A new advanced integral reactor of 330 MWt thermal capacity named SMART (System-Integrated Modular Advanced Reactor) is currently under development in Korea Atomic Energy Research Institute (KAERI) for multi-purpose applications. Modular once-through steam generator (SG) and self-pressurizing pressurizer equipped with wet thermal insulator and cooler are essential components of the SMART. The SMART provides safety systems such as Passive Residual Heat Removal System (PRHRS). In this study, a computer code for performance analysis of the PRHRS is developed by modeling relevant components and systems of the SMART. Using this computer code, a performance analysis of the PRHRS is performed in order to check whether the passive cooling concept using the PRHRS is feasible. The results of the analysis show that PRHRS of the SMART has excellent passive heat removal characteristics. 2 refs., 4 figs., 1 tab. (Author)

  19. Single and two-phase flow pressure drop for CANFLEX bundle

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joo Hwan; Jun, Ji Su; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Dimmick, G. R.; Bullock, D. E. [Atomic Energy of Canada Limited, Ontario (Canada)

    1998-12-31

    Friction factor and two-phase flow frictional multiplier for a CANFLEX bundle are newly developed and presented in this paper. CANFLEX as a 43-element fuel bundle has been developed jointly by AECL/KAERI to provide greater operational flexibility for CANDU reactor operators and designers. Friction factor and two-phase flow frictional multiplier have been developed by using the experimental data of pressure drops obtained from two series of Freon-134a (R-134a) CHF tests with a string of simulated CANFLEX bundles in a single phase and a two-phase flow conditions. The friction factor for a CANFLEX bundle is found to be about 20% higher than that of Blasius for a smooth circular pipe. The pressure drop predicted by using the new correlations of friction factor and two-phase frictional multiplier are well agreed with the experimental pressure drop data of CANFLEX bundle within {+-} 5% error. 11 refs., 5 figs. (Author)

  20. A Summary of Interfacial Heat Transfer Models and Correlations

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Sung Won; Cho, Hyung Kyu; Lee, Young Jin; Kim, Hee Chul; Jung, Young Jong; Kim, K. D. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-10-15

    A long term project has been launched in October 2006 to develop a plant safety analysis code. 5 organizations are joining together for the harmonious coworking to build up the code. In this project, KAERI takes the charge of the building up the physical models and correlations about the transport phenomena. The momentum and energy transfer terms as well as the mass are surveyed from the RELAP5/MOD3, RELAP5-3D, CATHARE, and TRAC-M does. Also the recent papers are surveyed. Among these resources, most of the CATHARE models are based on their own experiment and test results. Thus, the CATHARE models are only used as the comparison purposes. In this paper, a summary of the models and the correlations about the interfacial heat transfer are represented. These surveyed models and correlations will be tested numerically and one correlation is selected finally.

  1. The development of radiation protection and measurement technology - Characteristic studies for the radiation energy transport and radiological dose analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Kyung; Lee, Jae Ki; Kim, Soon Young; Kim, Jong Oh; Do, Man Suk [Hanyang University, Seoul (Korea, Republic of)

    1995-07-01

    Calculation of inherent response function of the .gamma.-ray detector, Development of the energy spectrum unfolding code for X-and .gamma.-ray spectra in calibration room, Calculation of the air scattering and room return effect in the neutron dosimeter calibration room for bare Cf and D{sub 2} O moderated Cf sources. The results of this projects are as follows; Obtainment of the unfolding code data library using inherent energy response function of the .gamma.-ray detector, Development of the accurate unfolding algorithm and computer code, verification of the code with known X-and .gamma.-ray spectrum, and direct application to calibrational practice, Preparation for basis of accurate calibration of neutron dosimeter by offering the scattering correction factor of neutron irradiation facility in KAERI 17 refs., 11 tabs., 25 figs. (author)

  2. Development of a far infrared free electron laser based on compact microtron

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Lee, Byung Cheol; Kim, Sun Kook; Jeong, Young Uk; Cho, Sung Oh

    1998-11-01

    As a result of the cooperative research between KAERI and BINP, a FIR FEL having tunable range of output wavelength from 30 {mu}m to 50 {mu}m. The peak power is 10kW at maximum. The micropulse width is 10 ps and the macropulse width is 5 {mu}s. The repetition rate of micropulses is 2.8 GHz and that of macropulses is 1 - 10 Hz. In addition to the FIR FEL system, many key technologies of high power FELs have been developed. Among them are there electron accelerator technology, design and optimization of electron beamline, design of undulator, measurement of magnetic field of undulators, high-voltage technology, optical cavity, etc.. (author). 10 refs., 11 tabs., 48figs.

  3. Verification and uncertainty evaluation of CASMO-3/MASTER nuclear analysis system

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jae Seung; Cho, Byung Oh; Joo, Han Kyu; Zee, Sung Quun; Lee, Chung Chan; Park, Sang Yoon

    2000-06-01

    MASTER is a nuclear design code developed by KAERI. It uses group constants generated by CASMO-3 developed by Studsvik. In this report the verification and evaluation of uncertainty were performed for the code system application in nuclear reactor core analysis and design. The verification is performed via various benchmark comparisons for static and transient core condition, and core follow calculations with startup physics test predictions of total 14 cycles of pressurized water reactors. Benchmark calculation include comparisons with reference solutions of IAEA and OECA/NEA problems and critical experiment measurements. The uncertainty evaluation is focused to safety related parameters such as power distribution, reactivity coefficients, control rod worth and core reactivity. It is concluded that CASMO-3/MASTER can be applied for PWR core nuclear analysis and design without any bias factors. Also, it is verified that the system can be applied for SMART core, via supplemental comparisons with reference calculations by MCNP which is a probabilistic nuclear calculation code.

  4. Sensitivity Test for Benchmark Analysis of EBR-II SHRT-17 using MARS-LMR

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chiwoong; Ha, Kwiseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    This study was conducted as a part of the IAEA Coordinated Research Project (CRP), 'Benchmark Analyses of an EBR-II Shutdown Heat Removal Test (SHRT)'. EBR-II SHRT 17 (Loss of flow) was analyzed with MARS-LMR, which is a safety analysis code for a Prototype GEN-IV Sodium-cooled Fast Reactor (PGSFR) has developed in KAERI. The current stage of the CRP is comparing blind test results with opened experimental data. Some influential parameters are selected for the sensitivity test of the EBR-II SHRT-17. The major goal of this study is to understand the behaviors of physical parameters and to make the modeling strategy for better estimation.

  5. Preliminary Conceptual Design for Safety Parameter display System of PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Hyunju; Seong, Seunghwan; Kim, Wansu; Kim, Donghoon; Son, Kwangseop; Jang, Gwisook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    A PGSFR (prototype Gen-IV sodium-cooled fast reactor) is under development at KAERI. A safety parameter display system (SPDS) should be designed for licensing the PGSFR in order to cope with the TMI action plan requirements. Thus, a preliminary conceptual design for the SPDS of PGSFR including licensing requirements, intrinsic function, critical variables and alarm legs for the SPDS of the PGSFR is studied herein. At first, some documents issued by NRC related to install a SPDS include the following: - NUREG-0737, Clarification of TMI Action Plan Requirements - NUREG-0696, Functional Criteria for Emergency Response Facilities - NUREG-0835, Human Factors Acceptance Criteria for the Safety Parameter display System, Draft Report for Comment. The preliminary concept design for the SPDS of the PGSFR was studied. In designing of the PGSFR, the studied design concept will be refined and implemented through further studies to acquire the approval of a safety analysis report of the PGSFR.

  6. A Preliminary PIRT Development Related to SWR Accidents from an SG Tube Failure

    Energy Technology Data Exchange (ETDEWEB)

    So, Dongsup; Jeong, Ji Young; Lee, Yong Bum [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The results of the PIRT, the uncertainties of the phenomena ranked as high priority can be reduced by an investigation or/and theoretical evaluation. The PIRT for IHTS due to SG tube rupture of Prototype GEN-IV Sodium cooled Fast Reactor (PGSFR) is on developing stage by the KAERI-ANL experts. These plausible phenomena can be applicable to the PIRT development of PGSFR having the similar concept of KALIMER-600. The Phenomena Identification and Ranking Table (PIRT) process was created as a systematic and documented means of completing a U. S. NRC's Code Scaling, Applicability, and Uncertainty exercise with a limited amount of resources. This paper describes a preliminary PIRT development for a Sodium-Water Reaction (SWR) accident with regard to a Steam Generator (SG) tube failure of the KALIMER-600 (Korea Advanced Liquid Metal Reactor). The plausible phenomena related to SWR accidents were developed.

  7. Implementation of the k{sub 0}-standardization Method for an Instrumental Neutron Activation Analysis: Use-k{sub 0}-IAEA Software as a Demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Moon, Jong Hwa; Kim, Sun Ha; Kim, Hark Rho [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Ho, Manh Dung [Nuclear Research Institute, Dalat (Viet Nam)

    2006-03-15

    Under the RCA post-doctoral program, from May 2005 through February 2006, it was an opportunity to review the present work being carried out in the Neutron Activation Analysis Laboratory, HANARO Center, KAERI. The scope of this research included: a calibration of the counting system, a characterization of the irradiation facility ,a validation of the established k{sub o}-NAA procedure.The k{sub o}-standardization method for an Neutron Activation Analysis(k{sub o}-NAA), which is becoming increasingly popular and widespread,is an absolute calibration technique where the nuclear data are replaced by compound nuclear constants which are experimentally determined. The k{sub o}-IAEA software distributed by the IAEA in 2005 was used as a demonstration for this work. The NAA no. 3 irradiation hole in the HANARO research reactor and the gamma-ray spectrometers No. 1 and 5 in the NAA Laboratory were used.

  8. Establishment of a radiological dose assessment system for HANARO emergency preparedness

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eun Han; Han, Moon Hee; Suh, Kyung Suk; Hwang, Won Tae; Choi, Young Gil

    1999-12-01

    A radiological dose assessment system has been established to calculate the three-dimensional wind field based on the observed data at meteorological towers, and to calculate the exposure dose in the radiological accidents or for emergency training. The wind fields program has been constructed to calculate the real-time wind field using the atmospheric stability and the diffusion parameters based on the meteorological data sets measured from two meteorological towers. The result is separated into the effective dose and thyroid dose with 4 age groups such as infant, children, teenage and adult. Dose rate and cumulated dose for above each termare calculated and repeated for the prediction and modification according to the elapsed time. The evaluated data sets are displayed on the map around KAERI site with social and environmental information which is made with GIS. (author)

  9. Transport modeling of sorbing tracers in artificial fractures

    Energy Technology Data Exchange (ETDEWEB)

    Keum, Dong Kwon; Baik, Min Hoon; Park, Chung Kyun; Cho, Young Hwan; Hahn, Phil Soo

    1998-02-01

    This study was performed as part of a fifty-man year attachment program between AECL (Atomic Energy Canada Limited) and KAERI. Three kinds of computer code, HDD, POMKAP and VAMKAP, were developed to predict transport of contaminants in fractured rock. MDDM was to calculate the mass transport of contaminants in a single fracture using a simple hydrodynamic dispersion diffusion model. POMKAP was to predict the mass transport of contaminants by a two-dimensional variable aperture model. In parallel with modeling, the validation of models was also performed through the analysis of the migration experimental data obtained in acrylic plastic and granite artificial fracture system at the Whiteshell laboratories, AECL, Canada. (author). 34 refs., 11 tabs., 76 figs.

  10. Modeling of gap cooling phenomena in LAVA-4 test using MELCOR

    Energy Technology Data Exchange (ETDEWEB)

    Park, J.H.; Park, S.Y.; Kim, S.D.; Song, Y.M.; Kim, D.H. [Korea Atomic Energy Research Inst., Daeduk (Korea)

    2000-07-01

    During the severe accident, the coolability of hot debris in the hemispherical lower vessel head has been an important issue concerning the plant safety. KAERI has launched the 'SONATA' experimental program and series of LAVA test have been performed to examine the existence of initial gap and its effect on the cooling of hot debris. A gap-cooling phenomenon was modeled and implemented into the lower plenum model in MELCOR. The calculation with considering the gap cooling phenomena shows a good prediction of the rapid cool clown of the vessel wall and the debris. But this model needs more refinement and evaluation against the experimental results before application to the plant. (author)

  11. HANARO radiation emergency plan

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Tai

    1997-10-15

    The emergency plan of HANARO (High-flux advanced Neutron Application Reactor) is prepared based on the Korea Atomic Law, the Civil Defence Law, Disaster Protection Law and the emergency related regulation guides such as the NUREG series from USNRC to ensure adequate response capabilities to the emergency event which would cause a significant risk to the KAERI staffs and the public near to the site. Periodic training and exercise for the reactor operators and emergency staffs will reduce accident risks and the release of radioactivities to the environment. The plan describes the organization and staff's duties in the radiation emergency, classification on the radiation accidents, urgent actions of reactor operators in the early state, emergency response activities, maintenance of emergency equipment, training and exercise to improve response capabilities against emergency accidents. (author). 1 tab., 5 figs.

  12. Preliminary design of the advanced quantum beam source

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Cheol; Lee, Jong Min; Jeong, Young Uk; Cho, Sung Oh; Yoo, Jae Gwon; Park, Seong Hee

    2000-07-01

    The preliminary design of the advanced quantum beam source based on a superconducting electron accelerator is presented. The advanced quantum beams include: high power free electron lasers, monochromatic X-rays and {gamma}-rays, high-power medium-energy electrons, high-flux pulsed neutrons, and high-flux monochromatic slow positron beam. The AQBS system is being re-designed, assuming that the SPS superconducting RF cavities used for LEP at CERN will revived as a main accelerator of the AQBS system at KAERI, after the decommissioning of LEP at the end of 2000. Technical issues of using the SPS superconducting RF cavities for the AQBS project are discussed in this report. The advanced quantum beams will be used for advanced researches in science and industries.

  13. A Study of a nuclear hydrogen production demonstration plant

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Jong Hwa and others [KAERI, Daejeon (Korea, Republic of); Bae, Ki Kwang [Korea Institute of Energy Research, Daejeon (Korea, Republic of); Jung, Kwang Deog [Korea Institute od Science and Technology, Seoul (Korea, Republic of)

    2007-03-15

    The current energy supply system is burdened environmental and supply problems. The concept of a hydrogen economy has been actively discussed worldwide. KAERI has set up a plan to demonstrate massive production of hydrogen using a VHTR by the early 2020s. The technological gap to meet this goal was identified during the past few years. The hydrogen production process, a process heat exchanger, the efficiency of an I/S thermochemical cycle, the manufacturing of components, the analysis tools of VHTR, and a coated particle fuel are key areas that require urgent development. Candidate NHDD plant designs based on a 200 MWth VHTR core and I/S thermochemical process have been studied and some of analysis results are presented in this paper.

  14. A state of the art on coastal environmental protection using radioisotope tracer technology

    CERN Document Server

    Jung, S H; Jin, J H; Kim, J B

    2002-01-01

    Construction of artificial structures has caused a sediment process change due to the variation of hydraulic condition in Korea. Subsequently we have a serious problem of shoaling for shoreline deformation, siltation of the harbor and shipping channel. To protect those abnormal environmental changes, a large estimate has been spent for additional construction such as outer wall facilities, littoral nourishment and dredging. Systematic long-term studies should be carried out to understand the causes of environmental change. In addition, comprehensive plan is required for its monitoring and prevention. The radioisotope application studies for coastal environmental protection have not been actively performed only in the developed countries like France, Canada, and Australia etc., but also in many developing countries like Poland, India. Since KAERI has performed two experiments in costal area of Korea in 1960s, no more study has been reported. Recently the studies of radiotracer application technology is getting...

  15. Development of technical information processing system(VI)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jee Hoh; Kim, Tae Hwan; Choi, Kwang; Chung, Hyun Sook; Keum, Jong Yong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    This project is to establish high-quality information circulation system by developing serials-control system to improve serials management from ordering to distributing and availability on R and D and to advance in quality of information service needed in R and D by fast retrieval and providing of research information with CD-Net. The results of the project are as follows. 1. Serials management process which covers from ordering to distributing have higher efficiency by development of subscription information system. 2. Systematic control on each issue of serials is achieved by development of serials checking system. 3. It is possible to provide vol. and no. information of issue received currently to researchers promptly by improvement of serials holding information system. 4. Retrieval of research information contained in various CD-ROM DB throughout KAERI-NET is possible by research on construction methods of CD-Net. 2 figs, 25 refs. (Author).

  16. Thermal hydraulic model descrition of TASS/SMR

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Han Young; Kim, H. C.; Chung, Y. J.; Lim, H. S.; Yang, S. H

    2001-04-01

    The TASS/SMR code has been developed for the safety analysis of SMART. The governing equations were applied only to the primary coolant system in TASS which had been developed at KAERI. In TASS/SMR, the solution method is improved so that the primary and secondary coolant systems are solved simultaneously. Besides the solution method, thermal-hydraulic models are incorporated, in TASS/SMR, such as non-condensible gas model, helical steam generator heat transfer model, and passive residual heat removal system (PRHRS) heat transfer model for the application to SMART. The governing equtions of TASS/SMR are based on the drift-flux model so that the accidents and transients accompaning with two-phase flow can be analized. This report describes the governing equations and solution methods used in TASS/SMR and also includes the description for the thermal hydraulic models for SMART design.

  17. Operation technology of air treatment system in nuclear facilities

    CERN Document Server

    Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

    2001-01-01

    Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

  18. Establishment of a computerized support system for the assessment of radiation exposure in nuclear emergency

    Energy Technology Data Exchange (ETDEWEB)

    Han, Moon Hui; Lee, Yeong Bok; Kim, Eun Han; Seo, Kyeong Seok; Hwang, Won Tae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Kim, Byeong Woo [Sungkyunkwan Univ., Seoul (Korea, Republic of)

    1995-12-15

    The main objective of this project is to provide a real-time dose assessment system which can be used in CARE system as a tool for radiological dose assessment and supporting decision-making in nuclear emergency. FADAS which has been developed as a nuclear long-term project of KAERI has been edited to be operated on HP workstation. And control program has been developed for the automatic control of the interface between FADAS and CARE modules. The environmental condition around Kori site has been investigated and the information related to the emergency planning such as population density, road network, and socio-environmental data have been displayed on the computer screen. It is necessary to prepare effective protective action suitable to a given environmental condition to minimize radiological exposure of the public. An algorithm for estimating the effectiveness of each protective action to a given situation has been proposed.

  19. Literature Survey of Copper Corrosion Modelling under Deep Geological Disposal Environment

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heui-Joo; Kook, Dong-Hak; Lee, Min-Soo; Choi, Heui-Joo

    2008-03-15

    As a one of the solution for the spent nuclear fuel problem, deep repository research have been under way in KAERI. To raise the resistance against repository cask corrosion, copper canister was adopted for the outer material of the cask. Duration of the repository with million year order makes the copper corrosion research under the repository environment very important and the corrosion modelling which could trace the real world precisely and predict the corrosion behavior very well is subsequently necessary. With in progress of plan to manufacture unique copper cask corresponding to our country repository system, survey for the preceding research papers in recent research direction and kernel points is expected to significant. This paper arranged the representative literatures for the important corrosion mechanism which are recently published.

  20. Neutron detectors for scattering experiments at HANARO

    Indian Academy of Sciences (India)

    Myungkook Moon; Changhee Lee; Jongkyu Cheon; Younghyun Choi; Harkrho Kim; Shraddha S Desai

    2008-11-01

    Position sensitive detectors (PSD) measure the distribution of scattered neutrons and are essential tools for neutron scattering experiments. Various types of neutron detectors used at neutron diffractometers are conventional tube detectors, 1-D and 2-D PSDs. Korea Atomic Energy Research Institute (KAERI) has been developing various kinds of PSDs to improve the instrument performance and to develop new scattering instruments. Our development work is initiated with 1-D PSD for residual stress analysis spectrometer and finally the technology is extended to development of 2-D PSD with planar and curved geometry. All PSDs are based on multiwire grid assembly with delay line readout method for position encoding, as the response is faster than charge division method and enables higher count rate capability. Design details and operational characteristics of some of the PSDs developed, for application at neutron scattering instruments are presented.

  1. State-of-the-art report on the development of liquid metal reactor fuel cladding materials in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Ho; Kuk, Il Hiun; Ryu, Woo Seog; Jang, Jin Sung; Rhee, Chang Kyu; Kim, Dae Whan; Park, Soon Dong; Kim, Woo Gon; Chung, Man Kyo; Han, Chang Hee

    1998-01-01

    PNC 1520 and PNC-FM5 have been developed as a cladding materials for LMR in Japan. PNC 1520 has superior swelling resistance and high temperature properties to PNC 31.6. And PNC-FMS steel has shown a high rupture stress as well as good neutron irradiation performance. In addition oxide dispersed ferritic steel (PNC-ODS) and 12Cr-8Mo steel have been developed. This report will give an insight for choosing and developing the materials to be applied to the KAERI prototype liquid metal reactor which is going to be operable in 2010 by analysis of the characteristics of cladding materials developed in Japan. (author). 39 refs., 2 tabs., 23 figs

  2. CONTRIBUTION OF HANARO IRRADIATION TECHNOLOGIES TO NATIONAL NUCLEAR R&D

    Directory of Open Access Journals (Sweden)

    KEE NAM CHOO

    2014-08-01

    Full Text Available HANARO is a multipurpose research reactor located at the Korea Atomic Energy Research Institute (KAERI. Since the commencement of its operation in 1995, various neutron irradiation facilities, such as rabbit irradiation facilities, fuel test loop (FTL facilities, capsule irradiation facilities, and neutron transmutation doping (NTD facilities, have been developed and actively utilized for various nuclear material irradiation tests requested by users from research institutes, universities, and industries. Most irradiation tests have been related to national R&D relevant to present nuclear power reactors such as the ageing management and safety evaluation of the components. Based on the accumulated experience as well as the sophisticated requirements of users, HANARO has recently supported national R&D projects relevant to new nuclear systems including the System-integrated Modular Advanced Reactor (SMART, research reactors, and future nuclear systems. This paper documents the current state and utilization of irradiation facilities in HANARO, and summarizes ongoing research efforts to deploy advanced irradiation technology.

  3. Review of Recent Aging-Related Degradation Occurrences of Structures and Passive Components in U.S. Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Nie,J.; Braverman, J.; Hofmayer, C.; Choun, Y.-S.; Kim, M.K.; Choi, I.-K.

    2009-04-02

    The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory (BNL) are collaborating to develop seismic capability evaluation technology for degraded structures and passive components (SPCs) under a multi-year research agreement. To better understand the status and characteristics of degradation of SPCs in nuclear power plants (NPPs), the first step in this multi-year research effort was to identify and evaluate degradation occurrences of SPCs in U.S. NPPs. This was performed by reviewing recent publicly available information sources to identify and evaluate the characteristics of degradation occurrences and then comparing the information to the observations in the past. Ten categories of SPCs that are applicable to Korean NPPs were identified, comprising of anchorage, concrete, containment, exchanger, filter, piping system, reactor pressure vessel, structural steel, tank, and vessel. Software tools were developed to expedite the review process. Results from this review effort were compared to previous data in the literature to characterize the overall degradation trends.

  4. Nuclear Instrumentation and Control Cyber Testbed Considerations – Lessons Learned

    Energy Technology Data Exchange (ETDEWEB)

    Jonathan Gray; Robert Anderson; Julio G. Rodriguez; Cheol-Kwon Lee

    2014-08-01

    Abstract: Identifying and understanding digital instrumentation and control (I&C) cyber vulnerabilities within nuclear power plants and other nuclear facilities, is critical if nation states desire to operate nuclear facilities safely, reliably, and securely. In order to demonstrate objective evidence that cyber vulnerabilities have been adequately identified and mitigated, a testbed representing a facility’s critical nuclear equipment must be replicated. Idaho National Laboratory (INL) has built and operated similar testbeds for common critical infrastructure I&C for over ten years. This experience developing, operating, and maintaining an I&C testbed in support of research identifying cyber vulnerabilities has led the Korean Atomic Energy Research Institute of the Republic of Korea to solicit the experiences of INL to help mitigate problems early in the design, development, operation, and maintenance of a similar testbed. The following information will discuss I&C testbed lessons learned and the impact of these experiences to KAERI.

  5. The Hydraulic Test Report for Non-instrumented Irradiation Test Rig of DUO-Cooled Annular Pellet

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dae Ho; Lee, Kang Hee; Shin, Chang Hwan; Yang, Yong Sik; Kim, Sun Ki; Bang, Je Geon; Song, Kun Woo

    2007-08-15

    This report presents the results of pressure drop test and vibration test for non-instrumented rig of Advanced PWR DUO-Fuel Annular Pellet which were designed and fabricated by KAERI. From the pressure drop test results, it is noted that the flow velocity across the non-instrumented rig of Advanced PWR DUO-Fuel Annular Pellet corresponding to the pressure drop of 200 kPa is measured to be about 8.30 kg/sec. Vibration frequency results for the non-instrumented rig at the pump spin frequency ranges from 19.0 to 32.0 Hz, RMS(Root Mean Square) displacement for the non-instrumented rig of Advanced PWR DUO-Fuel Annular Pellet is less than 7.25 m, and the maximum displacement is less than 31.27 {mu}m. This test was performed at the FIVPET facility.

  6. Concept development for HLW disposal research tunnel

    Energy Technology Data Exchange (ETDEWEB)

    Queon, S. K.; Kim, K. S.; Park, J. H.; Jeo, W. J.; Han, P. S. [KAERI, Taejon (Korea, Republic of)

    2003-10-01

    In order to dispose high-level radioactive waste in a geological formation, it is necessary to assess the safety of a disposal concept by excavating a research tunnel in the same geological formation as the host rock mass. The design concept of a research tunnel depends on the actual disposal concept, repository geometry, experiments to be carried at the tunnel, and geological conditions. In this study, analysis of the characteristics of the disposal research tunnel, which is planned to be constructed at KAERI site, calculation of the influence of basting impact on neighbor facilities, and computer simuation for mechanical stability analysis using a three-dimensional code, FLAC3D, had been carried out to develop the design concept of the research tunnel.

  7. Analysis of data from radioactive wastes treatment process and implementation of a data management applied program

    Energy Technology Data Exchange (ETDEWEB)

    Jeo, H. S.; Son, J. S.; Kim, T. K.; Kang, I. S.; Lee, Y. H [KAERI, Taejon (Korea, Republic of)

    2003-10-01

    As for the generated radioactive waste, a nuclide and a form are various, and by small quantity occurs the irregular times in KAERI. Record management of a radioactive waste personal history is an important element in disposal. A data collection of a liquid / solid radioactive waste treatment process of a research organization became necessary while developing the RAWMIS which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by treatment process. Data on the actual treatment process that is not limited experiment improve by a document, human traces, saving of material resources and improve with efficiency of tracking about a radioactive waste and a process and give help to radioactive waste material valance and inventory study.

  8. Numerical Research on LVDT Sensor for Electromagnet Rigidity Measurement of Bottom Mounted CRDM

    Energy Technology Data Exchange (ETDEWEB)

    Huh, Hyung; Lee, Jinhaeng; Cho, Yeonggarp [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The stepping motor directly drives the ball screw, and the nut of the ball screw makes the electromagnet move up and down along the guide tube. At this time the higher force of an electromagnet will greatly result in less position fluctuation of the armature for a given variation of loadings. The magnetic rigidity represents one of the most important characteristics of the electromagnet. For this reason, it is necessary to measure control rod position including sagging rate due to loadings exactly. Therefore, KAERI has developed electromagnet rigidity measuring sensor using LVDT. This paper presents the case numerical research of prototyping a LVDT sensor for BMCRDM. The results of a FEM in this work lead to the following conclusions: The FEM result for LVDT shows good linearity of dIsplacement vs. induced voltage between 0[mm] and ±15[mm] intervals. For the extension of linearity interval, additional research work is necessary for the configuration and arrangement of primary and secondary coils.

  9. A preliminary uncertainty analysis of phenomenological inputs employed in MAAP code using the SAUNA system

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. H.; Park, S. Y.; Kim, K. R.; Ahn, K. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2009-10-15

    Uncertainty analysis is an essential element of safety analysis of nuclear power plants, and especially on the increase as an essential methodology of safety assessment by computer codes. Recently, these efforts have been stepped up to apply the uncertainty methodology in severe accident analysis and PSA Level 2. From this point of view, a statistical sampling-based MAAP-specific platform for a severe accident uncertainty analysis, SAUNA, is being developed in KAERI. Its main purpose is to execute many simulations that are employed for uncertainty analysis. For its efficient implementation, the SAUNA system is composed of three related modules: Firstly, a module for preparing a statistical sampling matrix, secondly, a module for the dynamic linking between code and samples for code simulation, and thirdly, a postprocessing module for further analysis of the code simulation results. The main objective of this paper is to introduce the main functions of the SAUNA system and its example of implementation.

  10. Endurance test on IR rig for RI production

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Heung June; Youn, Y. J.; Han, H. S.; Hong, S. B.; Cho, Y. G.; Ryu, J. S

    2000-12-01

    This report presents the pressure drop, vibration and endurance test results for IR rig for RI production which were desigened and fabricated by KAERI. From the pressure drop test results, it is noted that the flow rate through the IR rig corresponding to the pressure drop of 200 kPa is measured to be about 3.12 kg/sec. Vibration frequency for the IR rig ranges from 13 to 17 Hz. RMS(Root Mean Square) displacement for the IR rig is less than 30 {mu}m, and the maximum displacement is less than 110{mu}m. These experimental results show that the design criteria of IR rig meet the HANARO limit conditions. Endurance test results show that the appreciable fretting wear for the IR rig does not occur, however tiny trace of wear between contact points is observed.

  11. The development of an advanced information management system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    Performing a PSA requires a lot of data to analyze, to evaluate the risk, to trace the process of results and to verify the results. KAERI is developing a PSA information database system, AIMS (Advanced Information Management System for PSA). The objective of AIMS development is to integrate and computerize all the distributed information of a PSA into a system and to enhance the accessibility to PSA information for all PSA related activities. We designed the PSA information database system for the following purposes: integrated PSA information management software, sensitivity analysis, quality assurance, anchor to another reliability database. The AIMS consists of a PSA Information database, Information browsing (searching) modules, and PSA automatic quantification manager modules.

  12. Fabrication of rare-earth bearing fuel slug by injection casting method

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Hwan; Song, Hoon; Kim, Hyung Tae; Kim, Ki Hwan; Lee, Chan Bock [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Herein, U.10wt%Zr fuel slugs containing 0, 3, and 7 wt%RE were prepared by an injection casting method and their characteristics were evaluated. The as-cast fuel slugs were generally sound and fabricated to the full length of the mold. However, the increased amount of the charged RE noticeably deteriorated the quality of the casting components such as melting crucible. Chemical analysis of the U.10Zr and U.10Zr.3RE slugs showed that the target composition was matched to within 1.0 wt%. In contrast, the composition of the U.10Zr.7RE fuel slug differed by as much as 4.6 wt% from the target. Therefore, more protective casting variables should be considered, when casting high RE-bearing fuel slugs. KAERI seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes in spent nuclear fuel into shorter-lived fission products.

  13. Analyses of bundle experiment data using MATRA-h

    Energy Technology Data Exchange (ETDEWEB)

    Lim, In Cheol; Chea, Hee Taek [Korea Atomic Energy Research Institute, Taejon (Korea)

    1998-06-01

    When the construction and operation license for HANARO was renewed in 1995, 25% of CHF penalty was imposed. The reason for this was that the validation work related to the CHF design calculation was not enough for the assurance of CHF margin. As a part of the works to recover this CHF penalty, MATRA-h was developed by implementing the new correlations for the heat transfer, CHF prediction, subcooled void to the MATRA-a, which is the modified version of COBRA-IV-I done by KAERI. Using MATRA-h, the subchannel analyses for the bundle experiment data were performed. The comparison of the code predictions with the experimental results, it was found that the code would give the conservative predictions as far as the CHF in the bundle geometry is concerned. (author). 12 refs., 25 figs., 16 tabs.

  14. Implementation of the networked computer based control system for PEFP 100MeV proton linear accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Song, Young Gi; Kwon, Hyeok Jung; Jang, Ji Ho; Cho, Yong Sub [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    The 100MeV Radio Frequency (RF) linac for the pulsed proton source is under development in KAERI. The main systems of the linac, such as the general timing control, the high power RF system, the control system of klystrons, the power supply system of magnets, the vacuum subsystem, and the cooling system, should be integrated into the control system of PEFP. Various subsystems units of the linac are to be made by other manufacturers with different standards. The technical integration will be based upon Experimental Physics and Industrial Control System (EPICS) software framework. The network attached computers, such as workstation, server, VME, and embedded system, will be applied as control devices. This paper is discussed on integration and implementation of the distributed control systems using networked computer systems.

  15. Neutron beam applications - Development of operational techniques for neutron four-circle diffractometer and structure determination of C{sub 16}H{sub 15}NO{sub 3}

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Moon Jib [Soonchunhyang University, Asan (Korea); Suh, Il Hwan [Chungnam National University, Taejon (Korea)

    1999-06-01

    We have been studied to find out the experimental methods and procedures for neutron diffraction method for neutron diffractometer in HANARO -the atomic research reactor in KAERI. We have studied experimental process for the neutron diffraction data analysis, using computer soft-wares such as SHELXS for the calculation the initial phase of crystal structure, SHELXL for refinement of atomic coordinate using least-squares method, ORTEP for the display of the calculated positions of molecule, and PATSEE for the calculation of the phase from the expected structure. In these studies, we analyzed the structure of test sample using these programs, and prepare the user's manual for these soft-wares. We have also studied on bending effect of monochromator in order to increase the intensity of neutron beam, and designed HRPD - High Resolution Powder Diffractometers. 7 refs., 6 figs. (Author)

  16. Evaluation of peaking factors uncertainty for CASMO-3

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kang Suk; Song, Jae Seung; Kim, Yong Rae; Ji, Seong Kyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-02-01

    This document evaluates the pin-to-box factor uncertainty based on using the CASMO-3 with 40-group J-library. Five CE criticals performed by Westinghouse, two by B and W and four RPI criticals were analyzed, using cross sections by CASMO-3. DOT was used for the core calculation. THis is one hof series of efforts to verify ADONIS procedure which is a new core design package under development by KAERI. The expected outcome of this analysis is CASMO-3 pin peak uncertainty applicable to CE type fuel assembly design. The evaluated uncertainty of peaking factors for CASMO-3 was 1.863%. 21 tabs., 23 figs., 12 refs. (Author) .new.

  17. Performance and scenario evaluation of PAFS through the LOFW accident in APR1400 by using MARS code

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Sung Won; Bae, Byoung Uhn; Yun, Byong Jo [Korea Atomic Energy Institute, Daejeon (Korea, Republic of)

    2009-07-01

    In order to enhance the safety feature of the APR1400 through the passive ways, the passive auxiliary feedwater system(PAFS) is under preliminary consideration by KAERI. For the successful adaptation of PAFS, accident scenario evaluation of PWR plant that is assumed to have the PAFS system should be performed. Condensing heat exchanger assemblies are installed at the exterior boundary of the containment building per one steam generator. The performance of the heat exchanger is designed to remove the decay heat of the fuel completely. In normal operation condition, PAFS system is not connected with the steam and feed lines. A Total Loss of Feed Water(TLOFW) accident is selected for the performance and scenario evaluation after the severity check. The PAFS connection valves are open at the signal of 25% level trip of steam generator. With the single failure assumption of PAFS open valve, the scenario propagations are calculated by using MARS code.

  18. Analogue studies in the Alligator Rivers Region of Australia. Contribution to the scientific basis for the performance assessment of proposed repository sites

    Energy Technology Data Exchange (ETDEWEB)

    Garnett, H.M.; Airey, P.L. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia); Sekine, Keiichi; Hahn, Pil-Soo; Ott, W.R.; Pescatore, C.

    1996-10-01

    The Analogue Studies in the Alligator Rivers Region (ASARR) project is coordinated by the OECD/NEA and involves ANSTO, JAERI, KAERI and the USNRC. Its aim is to contribute to the performance assessment of nuclear waste disposal sites through the building of confidence in predictive transport codes. The project is principally concerned with validating models of sub-surface retardation processes which underpin the codes. This paper will describe recent progress in extending sorption studies from reference minerals to natural materials. The first step in the laboratory program was to investigate uranium uptake on binary systems comprising ferrihydrite and kaolinite. Secondly, the significance of small levels of active minerals such as anatase in a standard kaolinite and iron nodules in geological samples from the Koongarra Uranium deposit is being assessed. Progress towards applying the natural analogue approach to a reference arid site will be reported. The scientific approaches of the individual laboratories are outlined in an annex. (author)

  19. A study on the establishment of nuclear cooperative relations and future direction between Korea and Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Yang, M. H.; Kim, H. S.; Chung, W. S.; Yun, S. W.; Ko, H. S.; Lee, J. K

    2000-10-01

    This study was carried out in order to review the cooperation with vietnam and establish and activate the cooperative relations with Vietnam. During the study, current status of use and development of nuclear energy in vietnam, were investigated including nuclear power plant and cooperative relations between two nations were also established. It was agreed through exchanges of visits of cooperation delegation; 1) exchange of visits of cooperation delegation, 2) holding of policy seminar for high level decision makers of Vietnam 3) cooperaton between KAERI/VAEC, 4) joint feasibility study for the construction of KSNP into Vietnam and technical presentation of KSNP. It is recommended that cooperaion with vietnam be implemented systematically through the long term based basic directions and integrated national strategies.

  20. Tuning data processing for DTL (drift tube linac)

    Energy Technology Data Exchange (ETDEWEB)

    Park, M. Y.; Seol, K. T.; Song, Y. G.; Kwon, H. J.; Cho, Y. S. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2004-07-01

    The 20 MeV DTL for PEFP proton accelerator is now constructing in KAERI site. The frequency tuning of the RF cavity is very important to obtain the required beam quality and also to reduce power loss. We established the measuring system and data processing algorithm for electric field measurement of PEFP DTL. The electric field is measured by using well-known bead perturbation method. Generally the frequency shift by small metal bead is measured but our system is based on the phase shift measure. The details for this system will be reported other paper in this conference. Next we established the data processing algorithm of the measured phase shift. We aim at two main results at this work. The first is to shorten the processing time and second is to have the reproducibility for various measurement conditions. We measured the phase shift of J-Parc (Japan proton accelerator research complex) DTL3 using our measuring system.

  1. Biological monitoring of radiation using indicators

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jin Kyu; Chun, Ki Jung; Lim, Yong Tak

    1998-06-01

    KAERI and INP(Poland) have been carried out parallel study and joint experiments on the major topics according to MOU about their cooperative project. The experimental materials were T-4430 clones. Main results of the cooperative project were made on {sup r}esponse of TSH mutation to low LET radiation, response of TSH mutation to neutrons, response of TSH to mixed irradiation with different radiations and synergism between radiation and environmental factors such as photo period and diurnal temperature difference. Both institutes have established wide variety of research techniques applicable to tradescantia study through the cooperation. These result of research can make the role of fundamental basis for the better relationship between Korea and Poland. (author). 46 refs., 11 tabs., 31 figs.

  2. The MEGAPIE-TEST project: Supporting research and lessons learned in first-of-a-kind spallation target technology

    Energy Technology Data Exchange (ETDEWEB)

    Fazio, C. [Forschungszentrum Karlsruhe GmbH, P.O. Box 3640, 76021 Karlsruhe (Germany)], E-mail: concetta.fazio@nuklear.fzk.de; Groeschel, F.; Wagner, W.; Thomsen, K.; Smith, B.L. [Paul Scherrer Institut, 5232 Villigen PSI (Switzerland); Stieglitz, R. [Forschungszentrum Karlsruhe GmbH, P.O. Box 3640, 76021 Karlsruhe (Germany); Zanini, L. [Paul Scherrer Institut, 5232 Villigen PSI (Switzerland); Guertin, A.; Cadiou, A. [SUBATECH Laboratory, CNRS/IN2P3-EMN-University, F-44307 Nantes (France); Henry, J. [Commissariat a l' energie atomique, 91191 Gif-sur-Yvette Cedex (France); Agostini, P. [Ente per le nuove Tecnologie, l' Energia e l' Ambiente, Localita Brasimone, 40032 Camugnano, Bologna (Italy); Dai, Y.; Heyck, H.; Dementjev, S. [Paul Scherrer Institut, 5232 Villigen PSI (Switzerland); Panebianco, S. [Commissariat a l' energie atomique, 91191 Gif-sur-Yvette Cedex (France); Almazouzi, A. [Studiecentrum voor Kernenergie/Centre d' Etude de l' Energie Nucleaire, Boeretang 200, 2400 Mol (Belgium); Eikenberg, J. [Paul Scherrer Institut, 5232 Villigen PSI (Switzerland); Letourneau, A.; Toussaint, J.C. [Commissariat a l' energie atomique, 91191 Gif-sur-Yvette Cedex (France); Janett, A. [Paul Scherrer Institut, 5232 Villigen PSI (Switzerland)] (and others)

    2008-06-15

    The megawatt pilot experiment (MEGAPIE) has been launched by six European institutions (PSI, FZK, CEA, SCK-CEN, ENEA and CNRS), JAEA (Japan), DOE (US) and KAERI (Korea) with the aim to carry out an experiment, in the SINQ target location at PSI (Switzerland), to demonstrate the safe operation of a liquid metal (lead-bismuth eutectic, LBE) spallation target hit by a {approx}1 MW proton beam. The European Commission has joined the MEGAPIE project through the 5-year (2001-2006) project named MEGAPIE-TEST. This project has been formally concluded with an International Workshop, where the results and the lessons learned during the project have been summarised. This work presents a review of the outcome of that Workshop.

  3. Nuclear Fusion Fuel Cycle Research Perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Hongsuk; Koo, Daeseo; Park, Jongcheol; Kim, Yeanjin [KAERI, Daejeon (Korea, Republic of); Yun, Sei-Hun [National Fusion Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    As a part of the International Thermonuclear Experimental Reactor (ITER) Project, we at the Korea Atomic Energy Research Institute (KAERI) and our National Fusion Research Institute (NFRI) colleagues are investigating nuclear fusion fuel cycle hardware including a nuclear fusion fuel Storage and Delivery System (SDS). To have a better knowledge of the nuclear fusion fuel cycle, we present our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). To have better knowledge of the nuclear fusion fuel cycle, we presented our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). Our efforts to enhance the tritium confinement will be continued for the development of cleaner nuclear fusion power plants.

  4. Evaluation of SPACE code for natural circulation test of Hanbit unit 2

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seyun; Kim, Minhee [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    SPACE (Safety and Performance Analysis Code for Nuclear Power Plants) has been developed by KHNP with the cooperation with KEPCO E and C and KAERI. SPACE code is expected to be applied to the safety analysis for LOCA (Loss of Coolant Accident) and Non-LOCA scenarios. SPACE code solves two-fluid, three-field governing equations and programmed with C++ computer language using object-oriented concepts. To evaluate the analysis capability for the passive cooling phenomenon in the actual nuclear power plant, a natural circulation test of Hanbit unit 2 was simulated with SPACE code. To evaluate the analysis capability for the passive cooling phenomenon in the actual nuclear power plant, a natural circulation test of Hanbit unit 2 was simulated with SPACE code. The major parameters of natural circulation in transient are well predicted in SPACE calculations when compared to the plant data. The SPACE code has sufficient capability to simulate passive cooling phenomena.

  5. Sensitivity study on critical flow models of SPACE for inadvertent opening of containment spray valve in Shin Kori unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seyun; Kim, Minhee [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    SPACE (Safety and Performance Analysis Code for Nuclear Power Plants) has been developed by KHNP with the cooperation with KEPCO E and C and KAERI. SPACE code is expected to be applied to the safety analysis for LOCA (Loss of Coolant Accident) and Non-LOCA scenarios. SPACE code solves two-fluid, three-field governing equations and programmed with C++ computer language using object-oriented concepts. To evaluate the analysis capability for the transient phenomena in the actual nuclear power plant, an inadvertent opening of spray valve in startup test phase of Shin Kori unit 1 was simulated with SPACE. To assess the critical flow models of SPACE, the calculation with several critical flow models were carried out. The simulations of an inadvertent opening of spray valve of Shin Kori unit 1 with several critical flow models were carried out. The calculated transient behaviors of major reactor parameters with four critical flow models generally show good agreement with the measured.

  6. Recent progress in development of radioisotope production

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Byung Mok [HANARO Center, Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-10-01

    The Korea multipurpose research reactor, HANARO(Hi-flux Advanced Neutron Application Reactor) is designed and constructed to obtain high density neutron flux (max. 5x10{sup 14} n/cm{sup 2}{center_dot}sec) with relatively low thermal output (30 MW) in order to utilize for various studies such as fuel and material test, radioisotope production, neutron activation analysis, neutron beam experiment, neutron transmutation doping, etc. HANARO has 32 vertical channels (3 in-core, 4 out-core, 25 reflector) and 7 horizontal channels. KAERI has constructed 4 concrete hot cells for production of Co-60, Ir-192, etc. and 6 lead hot cells for production of medical RIs(I-131, Mo-99, etc.). Other 11 lead hot cells will be completed by Feb. 1998 for production of Sm-153, Dy-165, Ho-166, etc. Clean room facilities were installed for production of radiopharmaceuticals. (author)

  7. Validation of GAMMA+ model for Evaluating Heat Transfer of VHTR core in Accident Conditions by CFD analysis

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Dongho; Yoon, Sujong; Park, Gooncherl; Cho, Hyoungkyu [Seoul National Univ., Seoul (Korea, Republic of)

    2013-05-15

    KAERI has established a plan to demonstrate massive production of hydrogen using a VHTR by the early 2020s. In addition the GAMMA+ code is developed to analyze VHTR thermo-fluid transients at KAERI. One of the candidate reactor designs for VHTR is prismatic modular reactor (PMR), of which reference reactor is the 600MWth GT-MHR. This type of reactor has a passive safety system. During the High Pressure Conduction Cooling (HPCC) or Low Pressure Conduction Cooling (LPCC) accident, the core heats up by decay heat and then starts to cool down by conduction and radiation cooling to the Reactor Cavity Cooling System (RCCS) through the prismatic core. In this mechanism, the solid conduction occurs in graphite and fuel blocks, and the gas conduction and radiation occurs in coolant holes and bypass gaps. It is important to predict conduction and radiation heat transfer in the core for safety analysis. Effective thermal conductivity is derived by Maxwell's far-field methodology Radiation effect is expressed as corresponding conductivity and added to gas conductivity. In this study, ETC model used in GAMMA+ code is validated with the commercial CFD code, CFX-13. In this study, the effective thermal conductivity model of the GAMMA+ was evaluated by comparison of CFD analysis. The CFD analysis was conducted for various numbers and volume fractions of coolant holes and temperatures. Although slight disagreement was shown for the cases run with small number of holes, the result of GAMMA+ model is accurate for the large numbers of holes sufficiently. Since there are 102 coolant holes and 210 fuel holes in a fuel block, it is concluded that GAMMA+ model is proper formula for predicting effective thermal conductivity of the VHTR fuel block. However, in high temperature region above 500 .deg. C, the GAMMA+ model underestimates the effective thermal conductivity since radiation heat transfer is not reflected precisely. Further researches on it seem to be necessary.

  8. A Study on the Promotion of Networking for International Training and Education in Nuclear Technology

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. J.; Lee, E. J.; Han, K. W. (and others)

    2007-04-15

    For the diversification of Korea's participation in the ANENT, the country contributed to the establishment of a new project (2007-2009) for the promotion of ANENT activities. Along the same, KAERI contributed to the development of cyber platform. Also, available course contents from IAEA were surveyed. In particular an approval course entitled as 'Energy Planning' was planned to be implemented in 2007. Finally, the ANENT web-portal including the cyber platform was operated and improved by upgrading and adding information and data. In order to promote the domestic cultivation of young scientists, Korea hosted 2007 WNU SI for the first time in Asia. KAERI staff was attached to the head quarter office of WNU to develop the curricula of WNU SI jointly. Keeping the basic structure of the original curricula, the developed curricula included Korean experience of self reliance in nuclear power technology and development of advanced technology. Methodology for the cooperation between ANENT and WNU was studied resulting in 2 ways. Primarily, it was suggested and prepared to produce cyber contents from 2007 WNU SI so that they can be up-loaded both on WNU web site and ANENT cyber platform. Secondly, cooperation in education and training activities was suggested to conduct exchange of students, joint development of cyber contents, operation of ANENT-WNU joint courses, development of reference curricula, and mutual recognition of credits and degrees. The methodology for the cooperation between ANENT and WNU will be implemented as follows: cooperation in the use of cyber contents from 2007 WNU SI will be produced during the event and they will be up-loaded both on WNU web site and ANENT cyber platform for common use; cooperation in education and training activities will be implemented by way of exchanging students, jointly developing cyber contents, operating ANENT-WNU joint courses, developing reference curricula, and realizing mutual recognition of credits and

  9. CANDU advanced fuel R and D programs for 1997 - 2006 in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Suk, H.C.; Yang, M.S.; Sim, K-S.; Yoo, K.J. [Korea Atomic Energy Research Inst., Yusong, Taejon (Korea, Republic of)

    1997-07-01

    KAERI has a comprehensive product development program of CANFLEX and DUPIC fuels to introduce them into CANDU reactors in Korea and a clear vision of how the product will evolve over the next 10 years. CANDU reactors are not the majority of nuclear power plants in Korea, but they produce significant electricity to contribute Korea's economic growth as well as to satisfy the need for energy. The key targets of the development program are safety enhancement, reduction of spent fuel volume, and economic improvements, using the inherent characteristics and advantages of CANDU technology The CANFLEX and DUPIC R and D programs are conducted currently under the second stage of Korea's Nuclear Energy R and D Project as a national mid- and long-term program over the next 10 years from 1997 to 2006. The specific activities of the programs have taken account of the domestic and international environment concerning on non-proliferation in the Peninsula of Korea. As the first of the development products in the short-term, the CANFLEX-NU fuel will be completely developed jointly by KAERI/AECL and will be useful for the older CANDU-6 Wolsong unit 1. As the second product, the CANFLEX-0.9 % equivalent SEU fuel is expected to be completely developed within the next decade. It will be used in CANDU-6 reactors in Korea immediately after the development, if the existing RU in the world is price competitive with natural uranium. The DUPIC R and D program, as a long term program, is expected to demonstrate the possibility of use of used PWR fuel in CANDU reactors in Korea during the next 10 years. The pilot scale fabrication facility would be completed around 2010. (author)

  10. Development of the coupled 3D Finite element module with FRAPCON3.4 for Simulation of pellet-cladding mechanical interaction

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Sang-Kyu; Lee, Sung-Uk; Lee, Eun-Ho; Yang, Dong-Yol [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Kim, Hyo-Chan; Yang, Yong-Sik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The fuel rod is composed of the pellet made of UO{sub 2} and the cladding made of zircaloy which covers the pellet and transfers the heat from the pellet to the coolant. In particular, pellet-cladding mechanical interaction(PCMI) causes the failure of the cladding. Therefore, PCMI simulation code is necessary to access this phenomenon. METEOR and TOUTATIS have been developed by CEA in France. These codes analyze the multiphysics behavior using axisymmetric, axially-stacked, one-dimensional representation. As these calculate the global rod shape, there is a weak point to represent local behavior. For this purpose, CAST3M, which is 3D-FE code, has been developed for TOUTATIS. Recently, ALCYONE has been developed from METEOR and TOUTATIS in order to analyze chemical-physics and thermo-mechanical aspects. In USA, INL also has developed BISON code with multidimensional capability. In this paper, NUFORM3D, which is able to calculate elasto-plastic and contact behavior as three dimensional finite element (FE) module, has been developed by KAERI and KAIST. The NUFORM3D, which is able to calculate elastoplastic and contact behavior as three-dimensional finite element (FE) module, has been developed by KAERI and KAIST. To evaluate PCMI behavior of fuel rod, NUFORM3D has been linked with FRAPCON-3.4. The power ramp database (REGATE) in the test reactor was employed. The linked NUFORM3D module is able to show bamboo-shape deformation of cladding and maximum stress due to its deformation that FRAPCON3.4 cannot obtain.

  11. Task Analysis of Emergency Operating Procedures for Generating Quantitative HRA Data

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yochan; Park, Jinkyun; Kim, Seunghwan; Choi, Sun Yeong; Jung, Wondea; Jang, Inseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    In this paper, the analysis results of the emergency task in the procedures (EOPs; emergency operating procedures) that can be observed from the simulator data are introduced. The task type, component type, system type, and additional information related with the performance of the operators were described. In addition, a prospective application of the analyzed information to HEP quantification process was discussed. In the probabilistic safety analysis (PSA) field, various human reliability analyses (HRAs) have been performed to produce estimates of human error probabilities (HEPs) for significant tasks in complex socio-technical systems. To this end, Many HRA methods have provided basic or nominal HEPs for typical tasks and the quantitative relations describing how a certain performance context or performance shaping factors (PSFs) affects the HEPs. In the HRA community, however, the necessity of appropriate and sufficient human performance data has been recently indicated. This is because a wide range of quantitative estimates in the previous HRA methods are not supported by solid empirical bases. Hence, there have been attempts to collect HRA supporting data. For example, KAERI has started to collect information on both unsafe acts of operators and the relevant PSFs. A characteristic of the database that is being developed at KAERI is that human errors and related PSF surrogates that can be objectively observable are collected from full-scope simulator experiences. In this environment, to produce concretely grounded bases of the HEPs, the traits or attributes of tasks where significant human errors can be observed should be definitely determined. The determined traits should be applicable to compare the HEPs on the traits with the data in previous HRA methods or databases. In this study, task characteristics in a Westinghouse type of EOPs were analyzed with the defining task, component, and system taxonomies.

  12. Evaluation of neutron irradiation embrittlement in the Korean reactor pressure vessel steels(I) (1st progress report)

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jun Hwa; Lee, Bong Sang; Park, Duck Gun; Byun, Tak Sang; Kim, Joo Hag; Oh, Yong Jun; Yoon, Ji Hyun; Chi, Sei Hwan; Kuk, Il Hyun [Korea Atomic Energy Research Institute, Taejon (Korea)

    1998-10-01

    The SA508-3 reactor pressure vessel materials degrade due to the application at high temperature, high pressure, and neutron irradiation. In the present study it is planned to examine the effects of neutron irradiation on the properties for assessing the integrity of domestic reactors. The key tests are the Charpy impact test, tensile test, static and dynamic fracture toughness test, J-R test. The additional tests for obtaining basic material properties, such as micro-hardness, microstructural properties, small punch energy etc., are also performed. The irradiation tests are being performed at HANARO of KAERI through the instrumented capsules designed by KAERI and the post-irradiation tests are being performed at IMEF(Irradiated Material Evaluation Facility) of material (UCN-4), Si+Al (YGN-5), UCN-4 weld metal, and UCN-4 HAZ. In the irradiation test the temperature should be controlled in the range of 290 {+-} 10 deg C and the test materials would be irradiated to 2 to 3 neutron fluence levels including the end-of-life fluence. The status of performing this project is that (1) the key data on mechanical properties, mainly related to the fracture toughness, of the unirradiated materials have been obtained, (2) the irradiation of the 1st instrumented capsule, a preliminary test capsule containing miniature specimens, has been completed and is being stored for testing in IMEF, and (3) the 2nd instrumented capsule is being manufactured and will be irradiated in the beginning or 1999. This report includes mainly the experimental methods and results. The status of the design and manufacturing of the instrumented capsules and specimens was also briefly described. (author). 13 refs., 15 figs., 10 tabs.

  13. Pressure drop and blower performance tests in very high temperature Helium Experimental LooP (HELP)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chan Soo; Hong, Sung Deok; Kim, Yong Wan [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    Korea Atomic Energy Research Institute (KAERI) has developed the gas loops to develop and verify the key components of the nuclear hydrogen production system. At the present, KAERI is operating a small scale gas loop for feasibility tests of process heat exchanger and a very high temperature Helium Experimental LooP (HELP) for verification tests of bench scale prototypes for high temperature key components in Very High Temperature gas cooled Reactor (VHTR). Figure 1 presents the HELP assembled with the key components. The size was designed for the verification test of a 150kW intermediate heat exchanger or the simulation test in a 1/6 scaled down fuel block. The loop consists of the primary loop and the secondary loop. The primary loop and the secondary loop simulate VHTR and intermediate loop in nuclear hydrogen production system, respectively. The loops were designed to withstand the maximum temperature of 1000 .Deg. C, the maximum pressure of 9.0 MPa, and the normal mass velocity of 0.5 kg/sec. The working fluid is helium as the actual coolant of VHTR. The primary loop is composed of a preheater, a high temperature heater, a hot gas duct, intermediate heat exchangers, a water cooled U tube heat exchanger, a gas bearing circulator, a passive venting system and gas filters. The secondary loop has the same system configuration as the primary loop except a high temperature heater. Two loops share a helium supply system, a helium purification system and the water loop for a cooling tower as Figure 2. In this study, the experimental results of the bypass line pressure drop and blower performance at the nitrogen condition are analyzed to predict the main line mass flow rates without heaters.

  14. Considerations on Cyber Security Assessments of Korean Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung-Woon; Song, Jae-Gu; Han, Kyung-Soo; Lee, Cheol Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kang, Mingyun [E-Gonggam Co. Ltd., Daejeon (Korea, Republic of)

    2015-10-15

    Korea Institute of Nuclear Nonproliferation and Control (KINAC) has prepared the regulatory standard RS-015 based on RG 5.71. RS-015 defines the elements of a cyber security program to be established in nuclear facilities and describes the security control items and relevant requirements. Cyber security assessments are important initial activities in a cyber security program for NPPs. Cyber security assessments can be performed in the following key steps: 1) Formation of a cyber security assessment team (CSAT); 2) Identification of critical systems and critical digital assets (CDAs); 3) Plant compliance checks with the security control requirements in RS-015. Through the assessments, the current status of security controls applied to NPPs can be found out. The assessments provide baseline data for remedial activities. Additional analyses with the results from the assessments should be performed before the implementation of remedial security controls. The cyber security team at the Korea Atomic Energy Research Institute (KAERI) has studied how to perform cyber security assessments for NPPs based on the regulatory requirements. Recently, KAERI's cyber security team has performed pilot cyber security assessments of a Korean NPP. Based on this assessment experience, considerations and checkpoints which would be helpful for full-scale cyber security assessments of Korean NPPs and the implementation of remedial security controls are discussed in this paper. Cyber security assessment is one of important and immediate activities for NPP cyber security. The quality of the first assessment will be a barometer for NPP cyber security. Hence cyber security assessments of Korean NPPs should be performed elaborately.

  15. Experimental investigation on the droplet entrainment from interfacial waves in air-water horizontal stratified flow

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, J. H.; Ha, K. S. [KAERI, Daejeon (Korea, Republic of); Jeong, H. Y. [Sejong University, Seoul (Korea, Republic of)

    2014-10-15

    The main purpose of the wire is to avoid collision between adjacent rods.. Furthermore, a vortex induced vibration can be mitigated by wire spacers. In this study, the RANS based CFD methodology using an innovative grid generation has been evaluated in the 7-pin, 37-pin, and 217-pin wire wrapped fuel assembly, which is using the general purpose commercial CFD code, CFX. The RANS-based CFD methodology using the innovative hexagonal grid generation with the in-house code and the GGI function of the CFX code has been evaluated in the 7-pin, 37-pin, and 217-pin wire wrapped fuel assembly. SFR (Sodium-cooled Fast Reactor) system is one of the nuclear reactors in which a recycling of transuranics (TRUs) by reusing spent nuclear fuel sustains the fission chain reaction. This situation strongly motivated Korea Atomic Energy Research Institute (KAERI) to start a Prototype Gen Sodium-cooled Fast Reactor (PGSFR) design project under the national nuclear R and D program. Generally, SFR system has tight package of the fuel bundle and the high power density. The fuel assembly of SFR system is consisted of wire wrapped fuel bundles with triangular loose array. The bundles of the SFR fuel assembly usually consisted of rods and wire spacers. The innovative RANS-based CFD methodology can remarkably reduce the number of meshes. Grid sensitivity study of the wall y grid scale with SST turbulence model in 7-pin fuel assembly has been carried out, and the uncertainty of friction factor was under the 6.0%. It has been validated that the GGI function of CFX code is very conservative interpolation function. The innovative RANS based CFD methodology can be successfully extended to real 217- pin wire-wrapped fuel assembly of KAERI 2014 PGSFR.

  16. The Effect of Duct Level on the Performance of Reactor Vault Cooling System in the PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Yeom, Sujin; Ryu, Seung Ho; Kim, Dehee; Lee, Tae-Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Development of the prototype gen-Ⅵ sodium-cooled fast reactor (PGSFR) has been ongoing in Korea Atomic Energy Research Institute (KAERI). A reactor vault cooling system (RVCS), one of passive decay heat removal systems (PDHRS), passively removes core decay heat by chimney effect when severe accidents occur. The air cooling path is located around containment vessel (CV). An air separator which divides the downstream air and the upstream air is installed between CV and the concrete wall. To design the RVCS, key design parameters such as stack height, gap size between the concrete wall and the air separator, gap size between the air separator and the CV, thickness and layer composition of the air separator have to be determined. A duct level is one of these design parameters. It denotes the height of the upstream air path and related to the heat transfer length from CV to air. The duct level should be optimized with considering structural reliability and heat removal performance. Thus, in this paper, the heat removal performance of RVCS is evaluated depends on the duct level using 1D system design code, that is developed by KAERI autonomously, and commercial CFD program for optimum design of RVCS In this paper, the heat removal performance of RVCS is evaluated depends on the duct level using PARS2- LMR code and commercial CFD program for optimum design of RVCS to satisfy both conflicting needs, structural reliability and cooling performance. As a result of PARS2-LMR code analysis, it was observed that the heat removal rate increases as increase of duct level and the geometrical conditions, that satisfy the design limitations, were obtained. To qualitatively observe the trends of local temperature distribution, CFD simulations were conducted and hotspots were observed at the upper region of ducts for the low duct level case.

  17. Reevaluation of photon activation yields of {sup 11}C. {sup 13}N, and {sup 15}O for the estimation of activity in gas and water induced by the operation of electron accelerates for medical use

    Energy Technology Data Exchange (ETDEWEB)

    Masumoto, Kazuyoshi; Matsumura, Hiroshi; Bessho, Kotaro; Toyoda, Akihiro [High Energy Accelerator Research Organization, Tsukuba (Japan); Kasako, Kazuaki [Shimizu Corporation, Tokyo (Japan)

    2016-09-15

    Activation of air and water in the electron linear accelerator for medical use has not been considered severely. By the new Japanese regulation for protection of radiation hazard, it became indispensable to evaluate of activation of air and water in the accelerator room. The measurement of induced activity in air and water components in the electron energy region of 10 to 20 MeV is very difficult, because this energy region is close to the threshold energy region of photonuclear reactions. Then, we measured the photonuclear reaction yields of {sup 13}N,{sup 15}O, and {sup 11}C by using the electron linear accelerator. Obtained data were compared with the data calculated by the Monte Carlo method. An activation experiment was performed at the Research Center for Electron Photon Science, Tohoku University. Highly purified SiO{sub 2}, Si{sub 3}N{sub 4}, and carbon disks were irradiated for 10 minutes by Bremsstrahlung converted by a tungsten plate. Induced activity from C, N, and O was obtained. Monte Carlo calculation was performed using MCNP5 and AERY (DCHAIN-SP) to simulate the experimental condition. Cross section data were adopted the KAERI dataset. In our experiment in hospital, calculated values were not agreed with experimental values. It might be three possible reasons as the cause of this deference, such as irradiation energy, calculation procedure and cross section data. Obtained data of this work, calculated and experimental values were good agreement with each other within one order. In this work, we used KAERI dataset of photonuclear reaction instead of JENDL. Therefore, it was found that the photonuclear cross section data of light elements are most important for yield calculation in these reactions. Further improvement for calculation using a new dataset JENDL/PD-2015 and considering electron energy spreading will be needed.

  18. Development of safety analysis technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y. B.; Kwon, Y. M.; Suk, S. D. [and others

    2005-03-01

    The MATRA-LMR-FB has been developed internally for the damage prevention as well as the safety assessment during a channel blockage accident and, as a the result, the quality of the code becomes comparable to that developed in the leading countries. For a code-to-code comparison, KAERI could have access to the SASSYS-1 through a bilateral collaboration between KAERI and ANL. The study could bring into the reliability improvements both on the reactivity models in the SSC-K and on the SSC-K prediction capability. It finally leads to the completion of the SSC-K version 1.3 resulting from the qualitative and quantitative code-to-code comparison. The preliminary analysis for a metal fueled LMR could also become possible with the MELT-III and the VENUS-II, which had originally been developed for the HCDA analysis with an oxidized fuel, by developing the relevant models For the development of the safety evaluation technology, the safety limits have been set up, and the analyses of the internal and external channel blockages in an assembly have also been performed. Besides, the more reliable analysis results on the key design concepts could be obtained by way of the methodology improvement resulting from the qualitative and quantitative comparison study. For an efficient and systematic control of the main project, the integration of the developed technologies and the establishment of their data base have been pursued. It has gone through the development of the process control with taking account of interfaces among the sub-projects, the overall coordination of the developed technologies, the data base for the design products, and so on.

  19. Comparison report of open calculations for ATLAS Domestic Standard Problem (DSP 02)

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ki Yong; Kim, Y. S.; Kang, K. H.; Cho, S.; Park, H. S.; Choi, N. H.; Kim, B. D.; Min, K. H.; Park, J. K.; Chun, H. G.; Yu, Xin Guo; Kim, H. T.; Song, C. H.; Sim, S. K.; Jeon, S. S.; Kim, S. Y.; Kang, D. G.; Choi, T. S.; Kim, Y. M.; Lim, S. G.; Kim, H. S.; Kang, D. H.; Lee, G. H.; Jang, M. J.

    2012-09-15

    KAERI (Korea Atomic Energy Research Institute) has been operating an integral effect test facility, the Advanced Thermal Hydraulic Test Loop for Accident Simulation (ATLAS) for transient and accident simulations of advanced pressurized water reactors (PWRs). By using the ATLAS, a high quality integral effect test database has been established for major design basis accidents of the APR1400. A Domestic Standard Problem (DSP) exercise using the ATLAS database was promoted in order to transfer the database to domestic nuclear industries and to contribute to improving safety analysis methodology for PWRs. This 2nd ATLAS DSP exercise was led by KAERI in collaboration with KINS since the successful completion of the 1st ATLAS DSP in 2009. This exercise aims at effective utilization of integral effect database obtained from the ATLAS, establishment of cooperation framework among the domestic nuclear industry, better understanding of thermal hydraulic phenomena, and investigation of the possible limitation of the existing best estimate safety analysis codes. A small break loss of coolant accident of 6 inch break at the cold leg was determined as a target scenario by considering its technical importance and by incorporating with interests from participants. Twelve domestic organizations joined this DSP 02 exercise. Finally, eleven out of the joined organizations submitted their calculation results, including universities, government, and nuclear industries. This DSP exercise was performed in an open calculation environment where the integral effect test data was open to participants prior to code calculations. This report includes all information of the 2nd ATLAS DSP (DSP 02) exercise as well as comparison results between the calculations and the experimental data.

  20. Preliminary Analysis of a Steam Line Break Accident with the MARS-KS code for the SMART Design with Passive Safety Systems

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Doohyuk; Ko, Yungjoo; Suh, Jaeseung [Hannam Univ., Daejeon (Korea, Republic of); Bae, Hwang; Ryu, Sunguk; Yi, Sungjae; Park, Hyunsik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    SMART has been developed by KAERI, and SMART-Standard Design Approval (SDA) was recently granted in 2012. A SMART design with Passive Safety System (PSS) features (called SMART-PSS) is being developed and added to the standard design of SMART by KAERI to improve its safety system. Active safety systems such as safety injection pumps will be replaced by a passive safety system, which is actuated only by the gravity force caused by the height difference. All tanks for the passive safety systems are higher than the injection nozzle, which is located around the reactor coolant pumps (RCPs). In this study, a preliminary analysis of the main steam line break accident (MSLB) was performed using the MARS-KS code to understand the general behavior of the SMART-PSS design and to prepare its validation test with the SMART-ITL (FESTA) facility. An anticipated accident for the main steam line break (MSLB) was performed using the MARS-KS code to understand the thermal-hydraulic behaviors of the SMART-PSS design. The preliminary analysis provides good insight into the passive safety system design features of the SMART-PSS and the thermal-hydraulic characteristics of the SMART design. The analysis results of the MSLB showed that the core water collapsed level inside the core support barrel was maintained high over the active core top level during the transient period. Therefore, the SMART-PSS design has satisfied the requirements to maintain the plant at a safe shutdown condition during 72 hours without AC power or operator action after an anticipated accident.

  1. Technology development for evaluation of operational quantities in radiation protection

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jang Lyul; Chang, S. Y.; Lee, L. T.; Kim, B. H.; Chung, K. K.; Lee, J. I.; Lim, G. S.; Kim, J. S.; Nam, Y. M.; Chang, J. K.; Kim, D. Y.; Yang, J. S

    2000-03-01

    A study on the fabrication of a new personal thermo-luminescence dosimeter, which can evaluate the personal dose equivalent H{sub p}(d), has been performed. Optimum conditions for fabrication of a LiF:Mg,Cu,Na,Si TL phosphor powder has been determined and a disc type TL pellet has been fabricated from this TL powder. Another type of CaSO{sub 4}:Dy,Mo TL material has been also fabricated. These two TL materials have shown greater TL sensitivity than the foreign-made commercial TL materials. Mono-energetic fluorescence X-ray from 8.6 keV to 75 keV for use in performance testing of the developed TLDs energy response have been constructed and evaluated for the performance of the purity, air kerma, beam uniformity and distribution, and scattered fraction of X-rays. Reference neutron field of a D{sub 2}O moderated {sup 252}Cf source was characterized and the irradiation system using {sup 226}Ra and {sup 137}Cs sources was installed to construct the environmental gamma reference radiation and the low-level gamma radiation. A capability of calibration and measurement of KAERI In Vivo counting system for transuranic elements in the lung has been evaluated through the participation in the overseas intercomparison study on the In Vivo radioactivity measurement. An improvement and advancement of KAERI lung counting technology have been made by the analysis off uncertainties from the assumption of uniform radioactivity distribution in the lung, experimental determination and comparing of detection efficiency with different lung sets, and mathematical efficiency calibration of In Vivo counting system. (author)

  2. Design Improvement of Iso-Kinetic Flow Sampling Device at Subchannel in a Wire-Wrapped 37-pin Fuel Assembly for a Sodium Cooled Fast Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong-Won; Kim, Hyungmo; Ko, Yung-Joo; Chang, Seok-Kyu; Choi, Hae Seob; Euh, Dong-kin; Lee, Hyeong-Yeon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    Securing the structural integrity of a fuel assembly during reactor operation is of utmost importance in order to prevent reactor severe accident like the Fukushima nuclear power plant through a flow characteristics tests with test assembly scaled down from a prototype reactor of a sodium-cooled fast reactor (SFR). To evaluate uncertainty is very important to ensure reliability at the results of the fuel assembly. Therefore the sub-channel analysis method is commonly used for the thermal hydraulic analysis of a SFR, a wire wrapped sub-channel type. In KAERI, two sub-channel analysis codes (SLTHEN, MATRA-LMR) are considered to utilize for the design of the prototype reactor. In this study, design improvement of iso-Kinetic flow sampling device at sub-channel in a wire-wrapped 37-pin fuel assembly for a sodium cooled fast reactor is conducted for decreasing misalignment sensitivity. The subchannel flow characteristics analysis method is commonly used for the thermal hydraulic analysis of a SFR, a wire wrapped subchannel type. In KAERI, two subchannel analysis codes are considered to be utilized for the design of the prototype reactor. In this study, the X-axis probe misalignment error is 2.5%, the Y-axis probe misalignment error is 0.9% and flowmeter and DA equipment error is 0.2%. As shown in above results, the misalignment error was the highest factor in uncertainty analysis. To solve the problem, design improvement of iso-kinetic flow sampling device at subchannel in a wire-wrapped 37-pin fuel assembly is practiced for decreasing misalignment sensitivity error.

  3. Promotion of Bilateral Cooperative Programs in Nuclear Human Resources Development

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Nam, Y. M. (and others)

    2009-08-15

    The purpose of this project is strengthening of bilateral cooperation with those countries for sharing Korea's technology, and providing of education and training on Korean experience regarding national nuclear policy, technology self reliance, and technology itself, in the field of nuclear power generation and the application of radioisotopes and radiation. This project covers an analysis on the need of nuclear human resource development in countries having interest in the introduction of nuclear power and/or promotion of the use of nuclear energy, and provision of courses on 'nuclear power policy, planning and management' and 'design and operation of nuclear research reactor, and application of radiation technology' along with the country specific needs. Education and training of key members in nuclear energy development from Egypt: It was implemented through bilateral cooperation and support by KOICA program. The first part, which targeted staff members from Egypt Nuclear Commission, was held for 2 months providing a KOICA course on policy, planning and management for nuclear power project, and second part was on the job training in Korea Hydro and Nuclear Power and Korea Institute of Nuclear Safety, KAERI respectively. On the job training of 1 scientist from Vietnam was implemented on the basis of bilateral cooperation in a research laboratory on radioactive waste treatment technology, at KAERI. Education and training for scientists from South East RCA countries were carried out for 11 participants from Vietnam, Thailand, Indonesia, China, Pakistan, Malaysia, Philippines, and Bangladesh. The course dealt with nuclear research reactor and radiation application technology. Development of nuclear education and training programs for key persons involved in nuclear power projects from countries of Middle East: The developed program consists of 15 courses addressing 3 technical levels, i.e. high level policy makers, middle level project

  4. Nuclear Manpower Training

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. J.; Han, K. W.; Lee, H. Y. and others

    2006-01-15

    Through the project on nuclear human resources development in 2005, the Nuclear Training Center of KAERI has provided 67 nuclear education and training courses for 3,658 persons from the domestic nuclear related organizations such as Government Agencies, nuclear industries, R and D institutes, universities, and public as well as from IAEA Member States. In addition, 6 students (MS and Ph D.) have taken nuclear technology related courses offered by UST-KAERI. The project has developed 8 programs and 12 courses. They includes programs for IAEA training, bilateral education and training, and in-house training as well as courses dealing with maintenance of nuclear power plants and management of electricity generation, thermal-hydraulics nuclear hydrogen, nuclear safeguards, radiation emergency preparedness and etc. National and international cooperation has been promoted. For ANENT, test operation, data loading and revision of the web-portal have been undertaken. Also the web-portal operation system has been established. For FNCA, NTC has cooperated for the establishment of a model of human resource development and the exchange of information/materials. With WNU, the NTC has made an effort for hosting 2007 WNU Summer Institute. The infrastructure for nuclear education and training has been strengthened. Basic directions for providing the customers with better service, This includes showing kindness to the customer, renovation of the interior of training facilities, and upgrading of web-based management system for learning and using facilities of NTC. Other efforts have resulted in the publication of 25 course materials (10 for international courses and 15 for national courses), and the improvement of education and training equipment. The International Nuclear Training and Education Center (INTEC), which was opened in 2002, has hosted 296 international and domestic events in 2005.

  5. Analysis of implicit and explicit lattice sensitivities using DRAGON

    Energy Technology Data Exchange (ETDEWEB)

    Ball, M.R., E-mail: ballmr@mcmaster.ca; Novog, D.R., E-mail: novog@mcmaster.ca; Luxat, J.C., E-mail: luxatj@mcmaster.ca

    2013-12-15

    Highlights: • We developed a way to propagate point-wise perturbations using only WIMS-D4 multigroup data. • The method inherently includes treatment of multi-group implicit sensitivities. • We compared our calculated sensitivities to an industry standard tool (TSUNAMI-1D). • In general, our results agreed well with TSUNAMI-1D. - Abstract: Deterministic lattice physics transport calculations are used extensively within the context of operational and safety analysis of nuclear power plants. As such the sensitivity and uncertainty in the evaluated nuclear data used to predict neutronic interactions and other key transport phenomena are critical topics for research. Sensitivity analysis of nuclear systems with respect to fundamental nuclear data using multi-energy-group discretization is complicated by the dilution dependency of multi-group macroscopic cross-sections as a result of resonance self-shielding. It has become common to group sensitivities into implicit and explicit effects to aid in the understanding of the nature of the sensitivities involved in the calculations, however the overall sensitivity is an integral of these effects. Explicit effects stem from perturbations performed for a specific nuclear data for a given isotope and at a specific energy, and their direct impact on the end figure of merit. Implicit effects stem from resonance self-shielding effects and can change the nature of their own sensitivities at other energies, or that for other reactions or even other isotopes. Quantification of the implicit sensitivity component involves some manner of treatment of resonance parameters in a way that is self-consistent with perturbations occurring in associated multi-group cross-sections. A procedure for assessing these implicit effects is described in the context of the Bondarenko method of self-shielding and implemented using a WIMS-D4 multi-group nuclear library and the lattice solver DRAGON. The resulting sensitivity results were compared

  6. Depletion calculations for the McClellan Nuclear Radiation Center.

    Energy Technology Data Exchange (ETDEWEB)

    Klann, R. T.; Newell, D. L.

    1997-12-08

    Depletion calculations have been performed for the McClellan reactor history from January 1990 through August 1996. A database has been generated for continuing use by operations personnel which contains the isotopic inventory for all fuel elements and fuel-followed control rods maintained at McClellan. The calculations are based on the three-dimensional diffusion theory code REBUS-3 which is available through the Radiation Safety Information Computational Center (RSICC). Burnup-dependent cross-sections were developed at zero power temperatures and full power temperatures using the WIMS code (also available through RSICC). WIMS is based on discretized transport theory to calculate the neutron flux as a function of energy and position in a one-dimensional cell. Based on the initial depletion calculations, a method was developed to allow operations personnel to perform depletion calculations and update the database with a minimal amount of effort. Depletion estimates and calculations can be performed by simply entering the core loading configuration, the position of the control rods at the start and end of cycle, the reactor power level, the duration of the reactor cycle, and the time since the last reactor cycle. The depletion and buildup of isotopes of interest (heavy metal isotopes, erbium isotopes, and fission product poisons) are calculated for all fuel elements and fuel-followed control rods in the MNRC inventory. The reactivity loss from burnup and buildup of fission product poisons and the peak xenon buildup after shutdown are also calculated. The reactivity loss from going from cold zero power to hot full power can also be calculated by using the temperature-dependent, burnup-dependent cross-sections. By calculating all of these reactivity effects, operations personnel are able to estimate the total excess reactivity necessary to run the reactor for the given cycle. This method has also been used to estimate the worth of individual control rods. Using this

  7. Development and installation of Picostrain sensors in structural systems

    Science.gov (United States)

    Sener, Joseph C.; Latta, Bernard M.; Ross, Jimmy D.

    2004-07-01

    The concept of the Picostrain sensor technology is based on a standard, commercially available, electrical cable assembly embedded in pavement or structural members. The concept has been developed through the 1990s and patented by the Idaho Transportation Department (ITD) in 2003. The objective of this new technology is to build an inexpensive, easily installed and maintained sensor system for the purposes of vehicle classification (VC), vehicle identification (VI), weigh-in-motion (WIM), and vehicle tracking (VT) applications along with real-time monitoring and evaluation of structural performance under static and dynamic traffic loading. It is intended, in the future, that these sensors will be further developed to replace curently utilized expensive embedded pavement and structural sensors for ultimate improvement of transportation decision-making and planning. This will also help to document the movement of people and goods along with the evironmental, social, economic and financial parameters with an emphasis on tracking movements in social life for security based upon the use of this durable and reliable transducers. Approximately, 400 sensors have been installed on and in the reinforced concrete structural members of the West Park Center River Crossing Bridge (Bridge) and the Micron Engineering Center (MEC) building (Building) at Boise State University (BSU) in Boise, Idaho, USA, since 1998. These sensors were installed: in bridge pile caps, piers, girders and decks; bridge abutment embankments; building footings, columns, beams, floor slabs; and, have been linked to instrument cabinets on site. These sensors installed structures may now be called "smart" structures since they contain a resident sensing system capable of maintaining a constant watch over the integrity of the structure. These sensing systems will be able to evaluate the applied loads, as well as the static and dynamic response of the structure. This paper introduces and describes the new

  8. Star Formation in Undergraduate ALFALFA Team Galaxy Groups and Clusters

    Science.gov (United States)

    Koopmann, Rebecca A.; Durbala, Adriana; Finn, Rose; Haynes, Martha P.; Coble, Kimberly A.; Craig, David W.; Hoffman, G. Lyle; Miller, Brendan P.; Crone-Odekon, Mary; O'Donoghue, Aileen A.; Troischt, Parker; Undergraduate ALFALFA Team; ALFALFA Team

    2017-01-01

    The Undergraduate ALFALFA Team (UAT) Groups project is a coordinated study of gas and star formation properties of galaxies in and around 36 nearby (zwork undertaken by faculty and students at different institutions within the UAT. Here we present results from our wide area Hα and broadband R imaging project carried out with the WIYN 0.9m+MOSAIC/HDI at KPNO, including an analysis of radial star formation rates and extents of galaxies in the NGC 5846, Abell 779, NRGb331, and HCG 69 groups/clusters. This work has been supported by NSF grant AST-1211005 and AST-1637339.

  9. Seismic Fragility Analysis of a Degraded Condensate Storage Tank

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J.; Braverman, J.; Hofmayer, C.; Choun, Y-S.; Kim, M.K.; Choi, I-K.

    2011-05-16

    The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory are conducting a collaborative research project to develop seismic capability evaluation technology for degraded structures and components in nuclear power plants (NPPs). One of the goals of this collaboration endeavor is to develop seismic fragility analysis methods that consider the potential effects of age-related degradation of structures, systems, and components (SSCs). The essential part of this collaboration is aimed at achieving a better understanding of the effects of aging on the performance of SSCs and ultimately on the safety of NPPs. A recent search of the degradation occurrences of structures and passive components (SPCs) showed that the rate of aging related degradation in NPPs was not significantly large but increasing, as the plants get older. The slow but increasing rate of degradation of SPCs can potentially affect the safety of the older plants and become an important factor in decision making in the current trend of extending the operating license period of the plants (e.g., in the U.S. from 40 years to 60 years, and even potentially to 80 years). The condition and performance of major aged NPP structures such as the containment contributes to the life span of a plant. A frequent misconception of such low degradation rate of SPCs is that such degradation may not pose significant risk to plant safety. However, under low probability high consequence initiating events, such as large earthquakes, SPCs that have slowly degraded over many years could potentially affect plant safety and these effects need to be better understood. As part of the KAERI-BNL collaboration, a condensate storage tank (CST) was analyzed to estimate its seismic fragility capacities under various postulated degradation scenarios. CSTs were shown to have a significant impact on the seismic core damage frequency of a nuclear power plant. The seismic fragility capacity of the CST was developed

  10. Conceptual Nuclear Design of a 20 MW Multipurpose Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Chul Gyo; Kim, Hak Sung; Park, Cheol [KAERI, Daejeon (Korea, Republic of); Nghiem, Huynh Ton; Vinh, Le Vinh; Dang, Vo Doan Hai [Dalat Nuclear Research Reactor, Hanoi (Viet Nam)

    2007-08-15

    A conceptual nuclear design of a 20 MW multi-purpose research reactor for Vietnam has been jointly done by the KAERI and the DNRI (VAEC). The AHR reference core in this report is a right water cooled and a heavy water reflected open-tank-in-pool type multipurpose research reactor with 20 MW. The rod type fuel of a dispersed U{sub 3}Si{sub 2}-Al with a density of 4.0 gU/cc is used as a fuel. The core consists of fourteen 36-element assemblies, four 18-element assemblies and has three in-core irradiation sites. The reflector tank filled with heavy water surrounds the core and provides rooms for various irradiation holes. Major analyses have been done for the relevant nuclear design parameters such as the neutron flux and power distributions, reactivity coefficients, control rod worths, etc. For the analysis, the MCNP, MVP, and HELIOS codes were used by KAERI and DNRI (VAEC). The results by MCNP (KAERI) and MVP (DNRI) showed good agreements and can be summarized as followings. For a clean, unperturbed core condition such that the fuels are all fresh and there are no irradiation holes in the reflector region, the fast neutron flux (E{sub n}{>=}1.0 MeV) reaches 1.47x10{sup 14} n/cm{sup 2}s and the maximum thermal neutron flux (E{sub n}{<=}0.625 eV) reaches 4.43x10{sup 14} n/cm{sup 2}s in the core region. In the reflector region, the thermal neutron peak occurs about 28 cm far from the core center and the maximum thermal neutron flux is estimated to be 4.09x10{sup 14} n/cm{sup 2}s. For the analysis of the equilibrium cycle core, the irradiation facilities in the reflector region were considered. The cycle length was estimated as 38 days long with a refueling scheme of replacing three 36-element fuel assemblies or replacing two 36-element and one 18-element fuel assemblies. The excess reactivity at a BOC was 103.4 mk, and 24.6 mk at a minimum was reserved at an EOC. The assembly average discharge burnup was 54.6% of initial U-235 loading. For the proposed fuel management

  11. A Study on the Adolescents Perception and Knowledge of Nuclear Energy Issues

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Eunjee; Nam, Youngmi [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Han, Kyongwon [ETRI, Daejeon (Korea, Republic of)

    2014-05-15

    The decreasing interest in nuclear energy in young people and a lack of basic understanding of it result in a negative influence on the formation of opinions and policy decision making regarding nuclear energy as a future energy source for a long-term view. International organizations including the International Atomic Energy Agency (IAEA) and countries dealing with nuclear related programs are promoting nuclear outreach to younger generations, in terms of an integrated, innovative, and sustainable approach. The same goes with the Korean nuclear community where diverse extra-curricular educational programs are being developed and provided to primary and middle school students, and to school teachers as well. Taking advantage of its unique research resources including experts and facilities, as a part of an adolescent and teacher's Nuclear Outreach project, KAERI-NTC (Nuclear Training and Education Center) is developing a education and training based nuclear outreach program is being developed, using the SAT (Systematic Approach Training) model. Systematic Approach to Training: the SAT model provides logical processes for developing and implementing education and training courses. KAERI-NTC has not only identified the nuclear education environment by conducting interviews with teachers, but has also collected opinions related to the development of a Nuclear Outreach program through expert consultation since last July. Based on this, KAERI-NTC developed a survey questionnaire to grasp the perception and the education demands of young students on nuclear energy and conducted a survey for 1,200 students a national scale. There is an increasing need for nuclear outreach to younger generations particularly due to the Fukushima NPP accident. Addressing this need by developing a SAT Model based educational nuclear outreach program, a survey on school students was conducted as part of a needs analysis. The survey show that the level of students' perception on

  12. Development of an S-band cavity-type beam position monitor for a high power THz free-electron laser

    Science.gov (United States)

    Noh, Seon Yeong; Kim, Eun-San; Hwang, Ji-Gwang; Heo, A.; won Jang, Si; Vinokurov, Nikolay A.; Jeong, Young UK; Hee Park, Seong; Jang, Kyu-Ha

    2015-01-01

    A cavity-type beam position monitor (BPM) has been developed for a compact terahertz (THz) free-electron laser (FEL) system and ultra-short pulsed electron Linac system at the Korea Atomic Energy Research Institute (KAERI). Compared with other types of BPMs, the cavity-type BPM has higher sensitivity and faster response time even at low charge levels. When electron beam passes through the cavity-type BPM, it excites the dipole mode of the cavity of which amplitude depends linearly on the beam offset from the center of the cavity. Signals from the BPM were measured as a function of the beam offset by using an oscilloscope. The microtron accelerator for the KAERI THz FEL produces the electron beam with an energy of 6.5 MeV and pulse length of 5 μs with a micropulse of 10-20 ps at the frequency of 2.801 GHz. The macropulse beam current is 40 mA. Because the microtron provides multi-bunch system, output signal would be the superposition of each single bunch. So high output signal can be obtained from superposition of each single bunch. The designed position resolution of the cavity-type BPM in multi-bunch is submicron. Our cavity-type BPM is made of aluminum and vacuum can be maintained by indium sealing without brazing process, resulting in easy modification and cost saving. The resonance frequency of the cavity-type BPM is 2.803 GHz and the cavity-type BPM dimensions are 200 × 220 mm (length × height) with a pipe diameter of 38 mm. The measured position sensitivity was 6.19 (mV/mm)/mA and the measured isolation between the X and Y axis was -39 dB. By measuring the thermal noise of system, position resolution of the cavity-type BPM was estimated to be less than 1 μm. In this article, we present the test results of the S-band cavity-type BPM and prove the feasibility of the beam position measurement with high resolution using this device.

  13. Development of an S-band cavity-type beam position monitor for a high power THz free-electron laser

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Seon Yeong; Kim, Eun-San, E-mail: eskim1@knu.ac.kr; Hwang, Ji-Gwang; Heo, A.; Won, Jang Si [Department of Physics, Kyungpook National University, Daegu 702-701 (Korea, Republic of); Vinokurov, Nikolay A.; Jeong, Young UK, E-mail: yujung@kaeri.re.kr; Hee Park, Seong; Jang, Kyu-Ha [WCI Center for Quantum-Beam-based Radiation Research, Korea Atomic Energy Research Institute, 989-111 Daedeok-Daero, Yuseong-gu, Daejeon (Korea, Republic of)

    2015-01-15

    A cavity-type beam position monitor (BPM) has been developed for a compact terahertz (THz) free-electron laser (FEL) system and ultra-short pulsed electron Linac system at the Korea Atomic Energy Research Institute (KAERI). Compared with other types of BPMs, the cavity-type BPM has higher sensitivity and faster response time even at low charge levels. When electron beam passes through the cavity-type BPM, it excites the dipole mode of the cavity of which amplitude depends linearly on the beam offset from the center of the cavity. Signals from the BPM were measured as a function of the beam offset by using an oscilloscope. The microtron accelerator for the KAERI THz FEL produces the electron beam with an energy of 6.5 MeV and pulse length of 5 μs with a micropulse of 10-20 ps at the frequency of 2.801 GHz. The macropulse beam current is 40 mA. Because the microtron provides multi-bunch system, output signal would be the superposition of each single bunch. So high output signal can be obtained from superposition of each single bunch. The designed position resolution of the cavity-type BPM in multi-bunch is submicron. Our cavity-type BPM is made of aluminum and vacuum can be maintained by indium sealing without brazing process, resulting in easy modification and cost saving. The resonance frequency of the cavity-type BPM is 2.803 GHz and the cavity-type BPM dimensions are 200 × 220 mm (length × height) with a pipe diameter of 38 mm. The measured position sensitivity was 6.19 (mV/mm)/mA and the measured isolation between the X and Y axis was −39 dB. By measuring the thermal noise of system, position resolution of the cavity-type BPM was estimated to be less than 1 μm. In this article, we present the test results of the S-band cavity-type BPM and prove the feasibility of the beam position measurement with high resolution using this device.

  14. Analysis of a double-pipe heat exchanger performance using heat structure coupling of MARS and CUPID

    Energy Technology Data Exchange (ETDEWEB)

    Amidua, M.; Kim, H. [Kyung Hee University, Yongin (Korea, Republic of); Cho, H. K. [Seoul National University, Seoul (Korea, Republic of)

    2015-10-15

    Thermal hydraulic phenomena in the inner tube of the double-pipe heat exchanger are expected to be reproducible by one-dimensional system analysis codes (MARS) if a proper condensation heat transfer coefficient is applied. Jeon et al (2013) and Cho et al (2013) conducted comprehensive reviews of the predictive capability of the condensation heat transfer models for the steam-water stratified flow. On the contrary, in the outer tube, a multidimensional analysis tool is required to incorporate the influence of azimuthal angle on the heat transfer rate from the inner tube outer wall to the outer tube fluid. Therefore, a coupled calculation between one dimensional system analysis code and a multidimensional computational fluid dynamics code is an attainable way to predict this effect with a reliable accuracy. CUPID is a three-dimensional computational multiphase fluid dynamics code developed by KAERI (Korea Atomic Energy Research Institute). According to Jeong et al (2010), the objective of the development is to support a resolution for the thermal hydraulic issues regarding the transient multi-dimensional twophase phenomena which can arise in an advanced light water reactor. It uses two-fluid model for the governing equations, which uses two sets of Navier-Stokes' equations for two phases. It can be used as either a typical CFD code or a component code (porous CFD code) depending on the length scale of the phenomena that need to be resolved. On the other hand, MARS is a best estimate thermalhydraulic system code and it was developed at KAERI by consolidating and restructuring the RELAP5/MOD3.2 code and COBRA-TF code (Cho et al., 2014). The MARS code has the capability to analyze best-estimated thermal hydraulic system. In this study, the coupled CUPID-MARS code was used for the simulation of a double-pipe heat exchanger. This paper presents the description of the heat exchanger, the coupling method, and the simulation results using the coupled code. The coupling

  15. Radioactivity determination of sealed pure beta-sources by surface dose measurements and Monte Carlo simulations

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chang Heon [Interdisciplinary Program in Radiation Applied Life Science, Seoul National University College of Medicine, Seoul (Korea, Republic of); Jung, Seongmoon [Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul (Korea, Republic of); Choi, Kanghyuk; Son, Kwang-Jae; Lee, Jun Sig [Hanaro Applications Research, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ye, Sung-Joon, E-mail: sye@snu.ac.kr [Interdisciplinary Program in Radiation Applied Life Science, Seoul National University College of Medicine, Seoul (Korea, Republic of); Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul (Korea, Republic of); Center for Convergence Research on Robotics, Advance Institutes of Convergence Technology, Seoul National University, Suwon (Korea, Republic of)

    2016-04-21

    This study aims to determine the activity of a sealed pure beta-source by measuring the surface dose rate using an extrapolation chamber. A conversion factor (cGy s{sup −1} Bq{sup −1}), which was defined as the ratio of surface dose rate to activity, can be calculated by Monte Carlo simulations of the extrapolation chamber measurement. To validate this hypothesis the certified activities of two standard pure beta-sources of Sr/Y-90 and Si/P-32 were compared with those determined by this method. In addition, a sealed test source of Sr/Y-90 was manufactured by the HANARO reactor group of KAERI (Korea Atomic Energy Research Institute) and used to further validate this method. The measured surface dose rates of the Sr/Y-90 and Si/P-32 standard sources were 4.615×10{sup −5} cGy s{sup −1} and 2.259×10{sup −5} cGy s{sup −1}, respectively. The calculated conversion factors of the two sources were 1.213×10{sup −8} cGy s{sup −1} Bq{sup −1} and 1.071×10{sup −8} cGy s{sup −1} Bq{sup −1}, respectively. Therefore, the activity of the standard Sr/Y-90 source was determined to be 3.995 kBq, which was 2.0% less than the certified value (4.077 kBq). For Si/P-32 the determined activity was 2.102 kBq, which was 6.6% larger than the certified activity (1.971 kBq). The activity of the Sr/Y-90 test source was determined to be 4.166 kBq, while the apparent activity reported by KAERI was 5.803 kBq. This large difference might be due to evaporation and diffusion of the source liquid during preparation and uncertainty in the amount of weighed aliquot of source liquid. The overall uncertainty involved in this method was determined to be 7.3%. We demonstrated that the activity of a sealed pure beta-source could be conveniently determined by complementary combination of measuring the surface dose rate and Monte Carlo simulations.

  16. I-NERI ANNUAL TECHNICAL PROGRESS REPORT: 2006-002-K, Separation of Fission Products from Molten LiCl-KCl Salt Used for Electrorefining of Metal Fuels

    Energy Technology Data Exchange (ETDEWEB)

    S. Frank

    2009-09-01

    An attractive alternative to the once-through disposal of electrorefiner salt is to selectively remove the active fission products from the salt and recycle the salt back to the electrorefiner (ER). This would allow salt reuse for some number of cycles before ultimate disposal of the salt in a ceramic waste form. Reuse of ER salt would, thus, greatly reduce the volume of ceramic waste produced during the pyroprocessing of spent nuclear fuel. This final portion of the joint I-NERI research project is to demonstrate the separation of fission products from molten ER salt by two methods previously selected during phase two (FY-08) of this project. The two methods selected were salt/zeolite contacting and rare-earth fission product precipitation by oxygen bubbling. The ER salt used in these tests came from the Mark-IV electrorefiner used to anodically dissolved driver fuel from the EBR-II reactor on the INL site. The tests were performed using the Hot Fuel Dissolution Apparatus (HFDA) located in the main cell of the Hot Fuels Examination Facility (HFEF) at the Materials and Fuels complex on the INL site. Results from these tests were evaluated during a joint meeting of KAERI and INL investigators to provide recommendations as to the future direction of fission product removal from electrorefiner salt that accumulate during spent fuel treatment. Additionally, work continued on kinetic measurements of surrogate quaternary salt systems to provide fundamental kinetics on the ion exchange system and to expand the equilibrium model system developed during the first two phases of this project. The specific objectives of the FY09 I-NERI research activities at the INL include the following: • Perform demonstration tests of the selected KAERI precipitation and INL salt/zeolite contacting processes for fission product removal using radioactive, fission product loaded ER salt • Continue kinetic studies of the quaternary Cs/Sr-LiCl-KCl system to determine the rate of ion

  17. Thermal hydraulic similarity analysis of the integral effect test facility for main steam line break events

    Energy Technology Data Exchange (ETDEWEB)

    Choi, K.Y.; Park, H.S.; Euh, D.J.; Kwon, T.S.; Baek, W.P. [Thermal Hydraulic Safety Research Division Korea Atomic Energy Research Institute 150 Dukjin-Dong, Yusong-Gu, Daejeon 305-353 (Korea, Republic of)

    2005-07-01

    Full text of publication follows: A thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), is being constructed at Korea Atomic Energy Research Institute (KAERI). The ATLAS is a 1/2 reduced height and 1/288 volume scaled test facility based on the design features of the APR1400, an evolutionary pressurized water reactor developed by Korean industry. The ATLAS will be used to get more realistic understanding of the thermal hydraulic phenomena following postulated events and to carry out performance evaluation and safety analysis of the reference plants. The MSLB (Main Steam Line Break) event is one of the representative non-LOCA events and thermalhydraulic phenomena following the event are to be investigated in the ATLAS. In this paper, thermal hydraulic similarity for MSLB events between the ATLAS and the prototype plant, APR1400 is assessed by using the MARS code, which is a multi-dimensional best-estimate thermal hydraulic code being developed by KAERI. Several cases including SLBFPLOOP and SLBFP are taken into account for similarity analysis in this paper. The neutronic effects such as moderator temperature coefficients and doppler reactivity in APR1400 are not considered in this study. The same control logics for the major sequence of events such as reactor trip, turbine trip, valve opening and actuation of the emergency cooling system are applied to the ATLAS and the APR1400. The present investigation is focused on the scaling and the reduced power effects on thermal hydraulic similarity after initiation of MSLB events. It is found that the ATLAS facility has the similar thermal hydraulic responses against the MSLB events. However, the initial high secondary pressure before the MSLB initiation resulted in different primary pressure and temperature progression from the APR1400. The break flow from the main steam line is found to be one of the most dominating parameters governing the transient

  18. Evaluation of CHF experimental data for non-square lattice 7-rod bundles

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Dae Hyun; Yoo, Y. J.; Kim, K. K.; Zee, S. Q

    2001-01-01

    A series of CHF experiments are conducted for 7-rod hexagonal test bundles in order to investigate the CHF characteristics of self-sustained square finned (SSF) rod bundles. The experiments are performed in the freon-loop and water-loop located at IPPE in Russia, and 609 data of freon-12 and 229 data of water are obtained from 7 kinds of test bundles classified by the combination of heated length and axial/radial power distributions. As the result of the evaluation of four representative CHF correlations, the EPRI-1 correlation reveals good prediction capability for SSF test bundles. The inlet parameter CHF correlation suggested by IPPE calculates the mean and the standard deviation of P/M for uniformly heated test bundles as 1.002 and 0.049, respectively. In spite of its excellent accuracy, the correlation has a discontinuity point at the boundary between the low velocity and high velocity conditions. KAERI's inlet parameter correlation eliminates this defect by introducing the complete evaporation model at low velocity condition, and calculates the mean and standard deviation of P/M as 0.095 and 0.062 for uniformly heated 496 data points, respectively. The mean/standard deviation of local parameter CHF correlations suggested by IPPE and KAERI are evaluated as 1.023/0.178 and 1.002/0.158, respectively. The inlet parameter correlation developed from uniformly heated test bundles tends to under-predict CHF about 3% for axially non-uniformly heated test bundles. On the other hand, the local parameter correlation reveals large scattering of P/M, and requires re-optimization of the correlation for non-uniform axial power distributions. As the result of the analysis of experimental data, it reveals that the correction model of axial power shapes suggested by IPPE is applicable to the inlet parameter correlations. For the test bundle of radial non-uniform power distribution, the physically unexpected results are obtained at some experimental conditions. In addition

  19. Analysis of Creep Rupture Data of Alloy 617 for VHTR Application

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woo Gon; Kim, Min Whan; Kim, Yong Wan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, Jae Young; Ekaputr, I. M. W. [Pukyong National Univ., Busan (Korea, Republic of)

    2013-10-15

    A new Alloy 617 Code Case is planned to be approved by 2015. In this study, the creep rupture data of Alloy 617, which were produced through a series of creep tests at 850-950 .deg. C at the Korea Atomic Energy Research Institute (KAERI), were analyzed using various creep laws, and the material constants were obtained and discussed.A very high temperature reactor (VHTR) is one of the most promising Gen-IV reactors for the economic production of electricity and hydrogen. Its major components are the reactor internals, reactor pressure vessel (RPV), hot gas ducts (HGD), and intermediate heat exchangers (IHX). Since the VHTR components are designed to be used for a 60 year lifetime at a high temperature, the creep behavior is very important for the design application due to creep damage during the long service life at elevated temperatures. Alloy 617 is a candidate IHX structural material because of its high temperature creep properties. However, the ASME design code for Alloy 617 was not developed for design use. Therefore, material works to complete the ASME Alloy 617 code case development are ongoing according to a next-generation nuclear plant (NGNP) research and development plan. Through this plan, a new Alloy 617 Code Case is planned to be approved by 2015. In this study, the creep rupture data of Alloy 617, which were produced through a series of creep tests at 850-950 .deg. C at the Korea Atomic Energy Research Institute (KAERI), were analyzed using various creep laws, and the material constants were obtained and discussed. Creep rupture data of Alloy 617 tested at 850-950 .deg. C were analyzed using various creep laws, and material constants were obtained. The MMGR reduced the data scattering, and was well fitted for straight line of m ≅ 1.0 as m=0.97. The MMGR showed a better plot than the MGR. In the plot of ZHP and stress, a straight line was for n'=5.87 regardless of the three different temperatures. Thus, it can be inferred that the same creep

  20. Estimation of the Alpha Factor Parameters Using the ICDE Database

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dae Il; Hwang, M. J.; Han, S. H

    2007-04-15

    Detailed common cause failure (CCF) analysis generally need for the data for CCF events of other nuclear power plants because the CCF events rarely occur. KAERI has been participated at the international common cause failure data exchange (ICDE) project to get the data for the CCF events. The operation office of the ICDE project sent the CCF event data for EDG to the KAERI at December 2006. As a pilot study, we performed the detailed CCF analysis of EDGs for Yonggwang Units 3 and 4 and Ulchin Units 3 and 4 using the ICDE database. There are two onsite EDGs for each NPP. When an offsite power and the two onsite EDGs are not available, one alternate AC (AAC) diesel generator (hereafter AAC) is provided. Two onsite EDGs and the AAC are manufactured by the same company, but they are designed differently. We estimated the Alpha Factor and the CCF probability for the cases where three EDGs were assumed to be identically designed, and for those were assumed to be not identically designed. For the cases where three EDGs were assumed to be identically designed, double CCF probabilities of Yonggwang Units 3/4 and Ulchin Units 3/4 for 'fails to start' were estimated as 2.20E-4 and 2.10E-4, respectively. Triple CCF probabilities of those were estimated as 2.39E-4 and 2.42E-4, respectively. As each NPP has no experience for 'fails to run', Yonggwang Units 3/4 and Ulchin Units 3/4 have the same CCF probability. The estimated double and triple CCF probabilities for 'fails to run' are 4.21E-4 and 4.61E-4, respectively. Quantification results show that the system unavailability for the cases where the three EDGs are identical is higher than that where the three EDGs are different. The estimated system unavailability of the former case was increased by 3.4% comparing with that of the latter. As a future study, a computerization work for the estimations of the CCF parameters will be performed.

  1. Methodology for Evaluating Safety System Operability using Virtual Parameter Network

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sukyoung; Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of); Kim, Jung Taek [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Tae Wan [Kepco International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-05-15

    KAERI (Korea Atomic Energy Research Institute) and UTK (University of Tennessee Knoxville) are working on the I-NERI project to suggest complement of this problem. This research propose the methodology which provide the alternative signal in case of unable guaranteed reliability of some instrumentation with KAERI. Proposed methodology is assumed that several instrumentations are working normally under the power supply condition because we do not consider the instrumentation survivability itself. Thus, concept of the Virtual Parameter Network (VPN) is used to identify the associations between plant parameters. This paper is extended version of the paper which was submitted last KNS meeting by changing the methodology and adding the result of the case study. In previous research, we used Artificial Neural Network (ANN) inferential technique for estimation model but every time this model showed different estimate value due to random bias each time. Therefore Auto-Associative Kernel Regression (AAKR) model which have same number of inputs and outputs is used to estimate. Also the importance measures in the previous method depend on estimation model but importance measure of improved method independent on estimation model. Also importance index of previous method depended on estimation model but importance index of improved method is independent on estimation model. In this study, we proposed the methodology to identify the internal state of power plant when severe accident happens also it has been validated through case study. SBLOCA which has large contribution to severe accident is considered as initiating event and relationship amongst parameter has been identified. VPN has ability to identify that which parameter has to be observed and which parameter can be alternative to the missing parameter when some instruments are failed in severe accident. In this study we have identified through results that commonly number 2, 3, 4 parameter has high connectivity while

  2. An Experience of Thermowell Design in RCP Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y. S.; Kim, B. D.; Youn, Y. J.; Jeon, W. J.; Kim, S.; Bae, B. U.; Cho, Y. J.; Choi, H. S.; Park, J. K; Cho, S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Flow rates for the test should vary in the range of 90% to 130% of rated flowrate under prototypic operational conditions, as shown in Table 1. Generally for the flow control, a combination of a control valve and an orifice was used in previous RCP test facilities. From the commissioning startup of the RCP test facility, it was found the combination of valve and orifice induced quite a large vibration for the RCP. As a solution to minimize the vibration and to facilitate the flowrate control, one of KAERI's staff suggested a variable restriction orifice (VRO), which controls most of the required flowrates except highest flowrates, as shown in Fig. 2. For the highest flowrates, e.g., around run-out flowrate (130%), control valves in bypass lines were also used to achieve required flowrates. From a performance test, it was found the VRO is very effective measures to control flowrates in the RCP test facility. During the commissioning startup operation, one of thermowells located at the upstream of the RCP was cracked due to high speed coolant velocity, which was - fortunately - found under a leakage test before running the RCP test loop. The cracked thermowell, whose tapered-shank was detached from the weld collar after uninstalling, is shown in Fig. 3. As can be seen the figure, most of the cross-section at the root of the thermowell shank was cracked. In this paper, an investigation of the integrity of thermowells in the RCP test facility was performed according to the current code and overall aspects on the thermowell designs were also discussed. An RCP test facility has been constructed in KAERI. During the commissioning startup operation, one of thermowells was cracked due to high speed coolant velocity. To complete the startup operation, a modified design of thermowells was proposed and all the original thermowells were replaced by the modified ones. From evaluation of the original and modified designs of thermowells according to the recent PTC code, the

  3. SSC-K code user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Y.M.; Lee, Y.B.; Chang, W.P.; Hahn, D

    2000-07-01

    The Supper System Code of KAERI (SSC-K) is a best-estimate system code for analyzing a variety of off-normal or accidents in the heat transport system of a pool type LMR design. It is being developed at Korea Atomic Energy Research Inititution (KAERI) on the basis of SSC-L, originally developed at BNL to analyze loop-type LMR transients. SSC-K can handle both designs of loop and pool type LMRs. SSC-K contains detailed mechanistic models of transient thermal, hydraulic, neutronic, and mechanical phenomena to describe the response of the reactor core, coolant, fuel elements, and structures to accident conditions. This report provides an overview of recent model developmentsvfor the SSC-K computer code, focusing on phenomenological model descriptions for new thermal, hydraulic, neutronic, and mechnaical modules. A comprehensive description of the models for pool-type reactor is given in Chapters 2 and 3; the steady-state plant characterization, prior to the initiation of transient is described in Chapter 2 and their transient counterparts are discussed in Chapter 3. In Chapter 4, a discussion on the intermediate heat exchanger (IHX) is presented. The IHX model of SSC-K is similar to that used in the SSC-L, except for some changes required for the pool-type configuration of reactor vessel. In Chapter 5, an electromagnetic (EM) pump is modeled as a component. There are two pump choices available in SSC-K; a centrifugal pump which was originally imbedded into the SSC-L, and an EM pump which was introduced for the KALIMER design. In Chapter 6, a model of passive safety decay heat removal system(PSDRS) is discussed, which removes decay heat through the reactor and containment vessel walls to the ambient air heat sink. In Chapter 7, models for various reactivity feedback effects are discussed. Reactivity effects of importance in fast reactor include the Doppler effect, effects of sodium density changes, effects of dimensional changes in core geometry. Finally in Chapter 8

  4. First observations with CONDOR, a 1.5 THz heterodyne receiver

    CERN Document Server

    Wiedner, M C; Bielau, F; Emprechtinger, M; Rettenbacher, K; Volgenau, N H; Graf, U; Honingh, C E; Jacobs, K; Vowinkel, B; Menten, K M; Nyman, L A A; Güsten, R; Philipp, S; Rabanus, D; Stutzki, J; Wyrowski, F

    2006-01-01

    The THz atmospheric windows centered at roughly 1.3 and 1.5~THz, contain numerous spectral lines of astronomical importance, including three high-J CO lines, the N+ line at 205 microns, and the ground transition of para-H2D+. The CO lines are tracers of hot (several 100K), dense gas; N+ is a cooling line of diffuse, ionized gas; the H2D+ line is a non-depleting tracer of cold (~20K), dense gas. As the THz lines benefit the study of diverse phenomena (from high-mass star-forming regions to the WIM to cold prestellar cores), we have built the CO N+ Deuterium Observations Receiver (CONDOR) to further explore the THz windows by ground-based observations. CONDOR was designed to be used at the Atacama Pathfinder EXperiment (APEX) and Stratospheric Observatory For Infrared Astronomy (SOFIA). CONDOR was installed at the APEX telescope and test observations were made to characterize the instrument. The combination of CONDOR on APEX successfully detected THz radiation from astronomical sources. CONDOR operated with typ...

  5. Effects of Cd(II) and Cu(II) on microbial characteristics in 2-chlorophenol-degradation anaerobic bioreactors

    Institute of Scientific and Technical Information of China (English)

    HUANG Aiqun; CHEN Hao; CHEN Ling; DAI Yalei; ZHAO Jianfu

    2008-01-01

    The effects of Cd2+ and CU2+ at 300 mg/L on anaerobic microbial communities that degrade 2.cholorophenol(2-CP) were examined. Based on the polymerase chain reaction (PCR) of 16S rDNA, bacterial community diversity and archaeal community structure were analyzed with denaturing gradient gel electrophoresis (DGGE) and cloning,respectively.Degradation capabilities of the anaerobic microbial community were drastically abated and the degradation efficiency of 2-CP was reduced to 60%after shock by Cu2+ and Cd2+, respectively.The bacterial community structure was disturbed and the biodiversity Was reduced after shock by Cu2+ and Cdz+ for 3 d.Some new metal-resistant microbes which could cope with the new condition appeared.The sequence analysis showed that there existed common Archaea species in control sludge and systems when treated with Cu2+ and Cd2+, such as Methanothrix soehngenii,Methanosaeta concilii,uncultured euryarchaeote, and so on.Both the abundance and diversity of archaeal species were altered with addition of Cd2+ and Cu2+ at high concentration.AIthough the abundance of the predominant archaeal species decreased wim Cd2+ and Cu2+ addition for 3 d.tIley recovered to some extent after 10 d.The diversity of archaeal species Was remarkably reduced after recovery for 10 d and the shift in archaeal composition seemed to be irreversible.The 2-CP-degradation anaerobic system was more sensitive to Cu2+ than Cd2+.

  6. Golden Jubilee Event for Cinema Fans

    CERN Multimedia

    2004-01-01

    As part of the Organisation's Fiftieth Anniversary celebrations the CERN CineClub will be showing a special series of films beginning with works by British, French, German, Norwegian and Spanish directors. The Club hopes to include films from all of the Member States in the programme. CERN's linguistic and cultural diversity will be celebrated from mid-February onwards when the CERN CineClub, whose summer English language film season will be familiar to many of you, plans to show a series of films from CERN's 20 Member States. The programme marks the CineClub's contribution to CERN's fiftieth anniversary festivities. The first film, "Four weddings and a funeral" (Mike Newell, 1994), will be shown in the Main Auditorium on 12 February. Next in the series will be films from Germany (Himmel über Berlin, or "The Wings of Desire", by Wim Wenders, 1987), Spain (Los Lunes al Sol, or "Mondays in the Sun", by Fernando Leon de Aranoa, 2002), France ( Diva , by Jean Jacques Beinex, 1981) and Norway (Elling, b...

  7. A Special Fiber Optic Sensor for Measuring Wheel Loads of Vehicles on Highways

    Directory of Open Access Journals (Sweden)

    Norman W. Garrick

    2008-04-01

    Full Text Available This paper presents results from an investigation on a special optical fiber as a load sensor for application in Weigh-in-Motion (WIM systems to measure wheel loads of vehicles traveling at normal speed on highways. The fiber used has a unique design with two concentric light guiding regions of different effective optical path lengths, which has the potential to enable direct measurement of magnitudes as well as locations of forces acting at multiple points along a single fiber. The optical characteristic of the fiber for intended sensing purpose was first assessed by a simple fiber bending experiment and by correlating the bend radii with the output light signal intensities. A simple laboratory load transmitting/fiber bending device was then designed and fabricated to appropriately bend the optical fiber under applied loads in order to make the fiber work as load sensor. The device with the optical fiber was tested under a universal loading machine and an actual vehicle wheel in the laboratory. The test results showed a good relationship between the magnitude of the applied load and the output optical signal changes. The results also showed a good correlation between the time delay between the inner and outer core light pulses and the distance of the applied load as measured from the output end of the fiber.

  8. A antessala de Siegfried Kracauer e Cees Nooteboom: Memória, história e imagem

    Directory of Open Access Journals (Sweden)

    Samanta Lopes Bergé

    2014-06-01

    Full Text Available http://dx.doi.org/10.5007/2175-7917.2014v19n1p134 Tendo como ponto de partida o romance Dia de Finados do escritor neerlandês Cees Nooteboom e History – the last things before the last, de Siegfried Kracauer, o presente ensaio tem como objetivo pensar as relações entre memória, história, imagem e o impacto das novas tecnologias nos modos de ver e ler. A memória e os subsequentes paralelos traçados por Kracauer entre filosofia e história, arte e fotografia/cinema serão abordados levando em consideração o momento atual da era digital e da mobilidade onde a televisão passa a ser vista, pouco a pouco, apenas como mero suporte. Da explosão do seriado americano True Detective ao inglês Black Mirror, o artigo busca fazer uma releitura do Culto da distração, publicado no jornal Frankfurter Zeitung em meados da década de 20 do século passado. As relações entre o historiador de Kracauer e o personagem principal do livro de Nooteboom também vêm à tona nos anjos de Wim Wenders, homens com asas, monstros histórico-literários.

  9. There's no language like our language, like no language we know. But how did it evolve?

    CERN Multimedia

    Wim de Geest

    2011-01-01

    Every normal child will rapidly acquire the native language to which it is exposed. It will do so with little teaching or coaching. A chimpanzee will fail to do so. Yet, chimpanzees are closer to humans, in genetic and evolutionary terms, than they are to gorillas. The only obvious and important deficit in the ape’s innate intelligence, as compared with man’s, is a missing faculty for using and understanding language. To determine how humans developed this unique capacity for language is the hardest problem in science. It is this problem the talk will address. The approach will be three pronged. In the first part Wim de Geest will attempt to present a couple of innovative insights made possible by the new Evo-Devo and the modern linguistics perspective. In the second part he shall illustrate what is specific for the human faculty of language in its narrow sense. Human linguistic communication is markedly discrete and recursive, to a degree that is obviously absent in other types ...

  10. Clinical Effects of Acupuncture after Surgical Operation in Patients with Prolapse of the Lumbar Intervertebral Disc

    Institute of Scientific and Technical Information of China (English)

    ZHAO Bin-xiu; WANG Kun-zheng; ZHAO Jie-xiu; WANG Chun-sheng; HUANG Xiag-hui; MA Shu-qiang; QIANG Hui

    2008-01-01

    Objective;To investigate the clinical effects of acupuncture after surgical operation in patients wim prolapse of the lumbar intervertebral disc(PLID).Methods;Sixty-nine patients in this series,who had undergone the removal of nucleus pulposus and the intervertebral fusion as well,were randomly divided into a treatment group of 35 cases and a control group of 34 cases.The former was treated by acupuncture and conventional rehabilitation therapy,and the latter only by the rehabilitation therapy.The therapeutic effects were evaluated according to the scoring system stipulated by Japanese Orthopedics Association(JOA).Results;In the treatment group,the average functional recovery rates in 3-month,6-month and one-year periods were respectively 49.93\t,90.3 1%and 95.08%;while the rates were repesctively 26.24%,63.42%and 71.36%in the control group,showing statistically significant difference between the two groups(P<0.05).Conclusions;Acupuncture can confirmatively promote the functional recovery for patients with prolapse of the lumbar intervertebral disc after surgical removal of nucleus pulposus and with intervertebral fusion.

  11. Full core analysis of IRIS reactor by using MCNPX.

    Science.gov (United States)

    Amin, E A; Bashter, I I; Hassan, Nabil M; Mustafa, S S

    2016-07-01

    This paper describes neutronic analysis for fresh fuelled IRIS (International Reactor Innovative and Secure) reactor by MCNPX code. The analysis included criticality calculations, radial power and axial power distribution, nuclear peaking factor and axial offset percent at the beginning of fuel cycle. The effective multiplication factor obtained by MCNPX code is compared with previous calculations by HELIOS/NESTLE, CASMO/SIMULATE, modified CORD-2 nodal calculations and SAS2H/KENO-V code systems. It is found that k-eff value obtained by MCNPX is closer to CORD-2 value. The radial and axial powers are compared with other published results carried out using SAS2H/KENO-V code. Moreover, the WIMS-D5 code is used for studying the effect of enriched boron in form of ZrB2 on the effective multiplication factor (K-eff) of the fuel pin. In this part of calculation, K-eff is calculated at different concentrations of Boron-10 in mg/cm at different stages of burnup of unit cell. The results of this part are compared with published results performed by HELIOS code.

  12. Components of Particle Emissions from Light-Duty Spark-Ignition Vehicles with Varying Aromatic Content and Octane Rating in Gasoline.

    Science.gov (United States)

    Short, Daniel Z; Vu, Diep; Durbin, Thomas D; Karavalakis, Georgios; Asa-Awuku, Akua

    2015-09-01

    Typical gasoline consists of varying concentrations of aromatic hydrocarbons and octane ratings. However, their impacts on particulate matter (PM) such as black carbon (BC) and water-soluble and insoluble particle compositions are not well-defined. This study tests seven 2012 model year vehicles, which include one port fuel injection (PFI) configured hybrid vehicle, one PFI vehicle, and six gasoline direct injection (GDI) vehicles. Each vehicle was driven on the Unified transient testing cycle (UC) using four different fuels. Three fuels had a constant octane rating of 87 with varied aromatic concentrations at 15%, 25%, and 35%. A fourth fuel with higher octane rating, 91, contained 35% aromatics. BC, PM mass, surface tension, and water-soluble organic mass (WSOM) fractions were measured. The water-insoluble mass (WIM) fraction of the vehicle emissions was estimated. Increasing fuel aromatic content increases BC emission factors (EFs) of transient cycles. BC concentrations were higher for the GDI vehicles than the PFI and hybrid vehicles, suggesting a potential climate impact for increased GDI vehicle production. Vehicle steady-state testing showed that the hygroscopicity of PM emissions at high speeds (70 mph; κ > 1) are much larger than emissions at low speeds (30 mph; κ < 0.1). Iso-paraffin content in the fuels was correlated to the decrease in WSOM emissions. Both aromatic content and vehicle speed increase the amount of hygroscopic material found in particle emissions.

  13. Shallow groundwater nitrogen responses to different land use managements in the riparian zone of Yuqiao Reservoir in North China

    Institute of Scientific and Technical Information of China (English)

    LU Haiming; YIN Chengqing

    2008-01-01

    This field study investigated the nitrogen concentrations in the shallow groundwater from an ephemeral stream and four land uses:cropland,two-year restored (2yr) and five-years restored (5yr) woodlands,fishponds,and the nitrogen flux in the riparian zone of Yuqiao Reservoir.The groundwater nitrate-N concentrations in cropland were the highest among the four land uses.Total dissolved nitrogen (TDN) and nitrate-N concentrations in the 2yr woodland were significantly (p<0.05) higher than in 5yr woodland.The lowest nitrogen concentrations were detected in fishponds.Nitrate-N was the main form in cropland and 2yr woodland,whereas both nitrate-N and diSSolved organic nitrogen (DON) were the main species in 5yr woodland and fishponds.But,ammonium-N was the main form in the ephemeral stream.During the rainy season,the groundwater flow wim dissolved nitrogen drains from upland into the reservoir along the hydraulic gradient.The woodland between the cropland and reservoir could act as a buffer to retain shallow groundwater nitrogen.The dominant form of ammonium-N in the groundwater TDN pool in ephemeral stream indicated that nitrogen from the village and orchard in upland flowed into the reservoir via subsurface flow.The fishpond Was not an important pollution source for nitrogen transfer via shallow groundwater.

  14. Spectrum of the Anomalous Microwave Emission in the North Celestial Pole with WMAP 7-Year Data

    Directory of Open Access Journals (Sweden)

    Anna Bonaldi

    2012-01-01

    Full Text Available We estimate the frequency spectrum of the diffuse anomalous microwave emission (AME on the North Celestial Pole (NCP region of the sky with the Correlated Component Analysis (CCA component separation method applied to WMAP 7-yr data. The NCP is a suitable region for this analysis because the AME is weakly contaminated by synchrotron and free-free emission. By modeling the AME component as a peaked spectrum we estimate the peak frequency to be 21.7±0.8 GHz, in agreement with previous analyses which favored νp < 23 GHz. The ability of our method to correctly recover the position of the peak is verified through simulations. We compare the estimated AME spectrum with theoretical spinning dust models to constrain the hydrogen density nH. The best results are obtained with densities around 0.2–0.3 cm−3, typical of warm ionised medium (WIM to warm neutral medium (WNM conditions. The degeneracy with the gas temperature prevents an accurate determination of nH, especially for low hydrogen ionization fractions, where densities of a few cm−3 are also allowed.

  15. Developpement d'une methode hybride pour le suivi du coeur et la gestion du combustible

    Science.gov (United States)

    Frenette, Eric

    The nuclear industry of CANDU reactors uses neutron physics methodologies (core follow-up, fuel management) that are considered out of date and do not reflect the latest developments in the field of neutronics. For instance, the software used by the reactor physics team in Gentilly-2, HQSIMEX 3, uses macroscopic cross sections ("grid-based" approach) calculated by two methods: (1) The "four factors" formula, an obsolete technique used in 1950; (2) The WIMS software, based on a microscopic cross section library. Among other method, the history-based approach is considered more precise but requires greater computing time. Processing a whole CANDU core follow-up through the history-based approach is not possible as of today with the actual computers, due to computing cost issues. The main goal of this research is to come up with a new strategy that will combine the interpolation technique of the "grid-based approach" with the isotopic depletion follow-up of the "history-based" approach.

  16. Computational simulation of fuel burnup estimation for research reactors plate type

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Nadia Rodrigues dos, E-mail: nadiasam@gmail.com [Instituto Federal de Educacao, Ciencia e Tecnologia do Rio de Janeiro (IFRJ), Paracambi, RJ (Brazil); Lima, Zelmo Rodrigues de; Moreira, Maria de Lourdes, E-mail: zrlima@ien.gov.br, E-mail: malu@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    The aim of this study is to estimate the spatial fuel burnup, through computational simulation, in two research reactors plate type, loaded with dispersion fuel: the benchmark Material Test Research - International Atomic Energy Agency (MTR-IAEA) and a typical multipurpose reactor (MR). The first composed of plates with uranium oxide dispersed in aluminum (UAlx-Al) and a second composed with uranium silicide (U{sub 3}Si{sub 2}) dispersed in aluminum. To develop this work we used the deterministic code, WIMSD-5B, which performs the cell calculation solving the neutron transport equation, and the DF3DQ code, written in FORTRAN, which solves the three-dimensional neutron diffusion equation using the finite difference method. The methodology used was adequate to estimate the spatial fuel burnup , as the results was in accordance with chosen benchmark, given satisfactorily to the proposal presented in this work, even showing the possibility to be applied to other research reactors. For future work are suggested simulations with other WIMS libraries, other settings core and fuel types. Comparisons the WIMSD-5B results with programs often employed in fuel burnup calculations and also others commercial programs, are suggested too. Another proposal is to estimate the fuel burnup, taking into account the thermohydraulics parameters and the Xenon production. (author)

  17. Summary of Meteorological Observations, Surface (SMOS), New River, North Carolina

    Science.gov (United States)

    1988-12-01

    0000000000000000000 ,aa z a- wim oieia N a z O.a -aaf0 W~~aC 0: OD00 0 0 0,o00 0 0 N Zha _I WW w ft a., u L W % 3 LACA 0: 00 EZW ~ ~ ~ ~ C P:N~ ’ m~-0 0 x xhad 0...1 01 0. CP9 0. O. 01 0.0 0’ 0. 0 01 000 4A p4.4.4 LD z - on M rP.00o 0*Y . In) ’P 0 - 0 N0Il4 4 0 0. z ka N 0 1 4X o :11 A 1 ZNC; 4O A f- D 1D N inOD0...0 0 A) 1 1D - 1- r -r 0 0 0 0 a 0 0 0 CY 0 0IN 0 0 0’ 01 0’ 0- In * V 011 𔃺 IAlll’ I-r -1- 010 .00’U*𔃺PI00-.t000 F., Ii %4 1 1 1 0000 0: 4! 9 6.9

  18. Laboratory spectroscopy of Mars Analogue materials and latest field results from Iceland and Eifel

    Science.gov (United States)

    Offringa, Marloes; Foing, Bernard H.

    2016-07-01

    We have established a collection of samples, and measured them in the laboratory towards a spectrometric database that could be used as a reference for future orbital or in situ measurements. We are using systematically for all samples UV-VIS and NIR reflectance spectrometers, and sporadically a Fourier Transform Infrared (FTIR) spectrometer, an X-Ray Fluorescence (XRF) spectrometer and a Raman laser spectrometer on control samples. We also used a documented set of Moon-Mars relevant minerals curated at VU Amsterdam, as well as samples retrieved from Mars analogue campaigns in Utah (Foing et al., 2011, 2016), Iceland (Mid-Atlantic ridge spreading and magma-ice interaction), La Réunion hot spot volcano and Eifel volcanic region (mixed hotspot and melt-ascent through crust fractures) from recent campaigns in 2015 and 2016.. We discuss samples spectral diagnostics of volcanic processes and hydrous alterations that can inform recent or upcoming measurements from Mars orbit or in situ rovers. Acknowledgements: we thank Dominic Doyle for ESTEC optical lab support, Euan Monaghan (Leiden U) for FTIR measurement support, Wim van Westrenen for access to VU samples, Oscar Kamps (Utrecht U), Aidan Cowley (EAC) and Matthias Sperl (DLR) for support discussions

  19. APS presents prizes in fluid dynamics and plasma physics

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-01

    This article reviews the presentation of the American Physical Society awards in fluid dynamics and plasma physics. The recipient of the plasma physics James Clerk Maxwell Prize was John M. Green for contributions to the theory of magnetohydrodynamics equilibria and ideal and resistive instabilities, for discovering the inverse scattering transform leading to soliton solutions of many nonlinear partial differential equations and for inventing the residue method of determining the transition to global chaos. The excellence in Plasma Physics Research Award was presented to Nathaniel A. Fisch for theoretical investigations of noninductive current generation in toroidally confined plasma. Wim Pieter Leemans received the Simon Ramo Award for experimental and simulational contributions to laser-plasma physics. William R. Sears was given the 1992 Fuid Dynamics Prize for contributions to the study of steady and unsteady aerodynamics, aeroacoustics, magnetoaerodynamics,and wind tunnel design. William C. Reynolds received the Otto Laporte Award for experimental, theoretical, and computational work in turbulence modeling and control and leadership in direct numerical simulation and large eddy simulation.

  20. Hα and [SII] Emission from Warm Ionized Gas in the Scutum-Centaurus Arm

    Science.gov (United States)

    Hill, Alex S.; Benjamin, Robert A.; Haffner, L. Matthew; Gostisha, Martin C.; Barger, Kathleen A.

    2014-06-01

    We present Wisconsin H-Alpha Mapper [SII] λ6716 and Hα spectroscopic maps of the warm ionized medium (WIM) in the Scutum-Centaurus Arm at Galactic longitudes 310° extinction-corrected Hα intensities (I_{{H} \\alpha }^c), we measure an exponential scale height of electron density squared in the arm of H_{n_e^2}= 0.30 \\, {kpc} (assuming a distance of 3.5 kpc), intermediate between that observed in the inner Galaxy and in the Perseus Arm. The [S II]/Hα line ratio is enhanced at large |z| and in sightlines with faint I_{{H} \\alpha }^c. We find that the [S II]/Hα line ratio has a power-law relationship with I_{{H} \\alpha }^c from a value of ≈1.0 at I_{{H} \\alpha }^creinforce the well-established picture in which the diffuse Hα emission is due primarily to emission from in situ photoionized gas, with scattered light only a minor contributor.

  1. ZOONET: perspectives on the evolution of animal form. Meeting report.

    Science.gov (United States)

    Fischer, Antje H L; Arboleda, Enrique; Egger, Bernhard; Hilbrant, Maarten; McGregor, Alistair P; Cole, Alison G; Daley, Allison C

    2009-11-15

    What drives evolution? This was one of the main questions raised at the final ZOONET meeting in Budapest, Hungary, in November 2008. The meeting marked the conclusion of ZOONET, an EU-funded Marie-Curie Research Training Network comprising nine research groups from all over Europe (Max Telford, University College London; Michael Akam, University of Cambridge; Detlev Arendt, EMBL Heidelberg; Maria Ina Arnone, Stazione Zoologica Anton Dohrn Napoli; Michalis Averof, IMBB Heraklion; Graham Budd, Uppsala University; Richard Copley, University of Oxford; Wim Damen, University of Cologne; Ernst Wimmer, University of Göttingen). ZOONET meetings and practical courses held during the past four years provided researchers from diverse backgrounds--bioinformatics, phylogenetics, embryology, palaeontology, and developmental and molecular biology--the opportunity to discuss their work under a common umbrella of evolutionary developmental biology (Evo Devo). The Budapest meeting emphasized in-depth discussions of the key concepts defining Evo Devo, and bringing together ZOONET researchers with external speakers who were invited to present their views on the evolution of animal form. The discussion sessions addressed four main topics: the driving forces of evolution, segmentation, fossils and phylogeny, and the future of Evo Devo.

  2. MTR core loading pattern optimization using burnup dependent group constants

    Directory of Open Access Journals (Sweden)

    Iqbal Masood

    2008-01-01

    Full Text Available A diffusion theory based MTR fuel management methodology has been developed for finding superior core loading patterns at any stage for MTR systems, keeping track of burnup of individual fuel assemblies throughout their history. It is based on using burnup dependent group constants obtained by the WIMS-D/4 computer code for standard fuel elements and control fuel elements. This methodology has been implemented in a computer program named BFMTR, which carries out detailed five group diffusion theory calculations using the CITATION code as a subroutine. The core-wide spatial flux and power profiles thus obtained are used for calculating the peak-to-average power and flux-ratios along with the available excess reactivity of the system. The fuel manager can use the BFMTR code for loading pattern optimization for maximizing the excess reactivity, keeping the peak-to-average power as well as flux-ratio within constraints. The results obtained by the BFMTR code have been found to be in good agreement with the corresponding experimental values for the equilibrium core of the Pakistan Research Reactor-1.

  3. Measurement of the composition of noble-metal particles in high-burnup CANDU fuel by wavelength dispersive X-ray microanalysis

    Energy Technology Data Exchange (ETDEWEB)

    Hocking, W.H.; Szostak, F.J

    1999-09-01

    An investigation of the composition of the metallic inclusions in CANDU fuel, which contain Mo, Tc, Ru, Rh and Pd, has been conducted as a function of burnup by wavelength dispersive X-ray (WDX) microanalysis. Quantitative measurements were performed on micrometer sized particles embedded in thin sections of fuel using elemental standards and the ZAF method. Because the fission yields of the noble metals change with burnup, as a consequence of a shift from almost entirely {sup 235}U fission to mainly {sup 239}Pu fission, their inventories were calculated from the fuel power histories using the WIMS-Origin code for comparison with experiment. Contrary to expectations that the oxygen potential would be buffered by progressive Mo oxidation, little evidence was obtained for reduced incorporation of Mo in the noble-metal particles at high burnup. These surprising results are discussed with respect to the oxygen balance in irradiated CANDU fuels and the likely intrinsic and extrinsic sinks for excess oxygen. (author)

  4. Reaching the teachers

    CERN Multimedia

    2001-01-01

    The fourth edition of CERN's High School Teachers programme welcomed 38 teachers to the Laboratory this July. For three weeks the teachers were immersed in the life of CERN, giving them a unique experience to take back to their classrooms.   Participants and organisers of the HST 2001 programme. The pupils of the teachers who attended the High School Teachers (HST) programme at CERN will notice a difference when they meet their teachers at the beginning of next term. They'll see a new-found enthusiasm in their eyes, and this will be thanks to the three weeks they spent at the Laboratory attending the summer students' lectures and working with other teachers from around the world. 'This experience fires you up again!,' explains Wim Peeters, a Belgian teacher at CERN for the second time. For many teachers of physics, university is a long time ago. Physics research has moved on, and there are many new things to learn. That's why CERN has the HST, so that teachers can mix with university students in ...

  5. Numerical simulation of influence of material parameters on splitting spinning of aluminum alloy

    Institute of Scientific and Technical Information of China (English)

    HUANG Liang; YANG He; ZHAN Mei; HU Li-jin

    2008-01-01

    During the splitting spinning process,the material parameters of disk blank have a significant effect on the determination of forming parameters and the quality of deformed blank.The influence laws of material parameters,including yield stress.hardening exponent and elastic modulus,on splitting spinning force,splitting spinning moment,degree of inhomogeneous deformation and quality of flange (average thickness and average deviation angle) were investigated by 3D-FE numerical simulation based on elasto-plastic dynamic explicit FEM under ABAQUS/Explicit environment.The results show that.the splitting spinning force and the splitting spinning moment increase wim the increase of yield stress.hardening exponent and elastic modulus.The degree of inhomogeneous deformation increases with the decrease of yield stress and hardening exponent and the increase of elastic modulus.The average thickness of flange increases with the decrease of yield stress and the increase of hardening exponent and elastic modulus.The average deviation angle of upper surface increases with the increase of yield stress and the decrease of hardening exponent and elastic modulus.The average deviation angle of lower surface increases with the decrease of yield stress.hardening exponent and elastic modulus.Meanwhile,the corresponding variation ranges are given.The achievements may serve as an important guide for selecting the reasonable processing parameters of splitting spinning based on different aluminum alloys,and are very significant for optimum design and precision control of the splitting spinning process.

  6. Shattering and coagulation of dust grains in interstellar turbulence

    CERN Document Server

    Hirashita, Hiroyuki

    2008-01-01

    We investigate shattering and coagulation of dust grains in turbulent interstellar medium (ISM). The typical velocity of dust grain as a function of grain size has been calculated for various ISM phases based on a theory of grain dynamics in compressible magnetohydrodynamic turbulence. In this paper, we develop a scheme of grain shattering and coagulation and apply it to turbulent ISM by using the grain velocities predicted by the above turbulence theory. Since large grains tend to acquire large velocity dispersions as shown by earlier studies, large grains tend to be shattered. Large shattering effects are indeed seen in warm ionized medium (WIM) within a few Myr for grains with radius $a\\ga 10^{-6}$ cm. We also show that shattering in warm neutral medium (WNM) can limit the largest grain size in ISM ($a\\sim 2\\times 10^{-5} \\mathrm{cm}$). On the other hand, coagulation tends to modify small grains since it only occurs when the grain velocity is small enough. Coagulation significantly modifies the grain size ...

  7. Fuel Burnup and Fuel Pool Shielding Analysis for Bushehr Nuclear Reactor VVER-1000

    Science.gov (United States)

    Hadad, Kamal; Ayobian, Navid

    Bushehr Nuclear power plant (BNPP) is currently under construction. The VVER-1000 reactor will be loaded with 126 tons of about 4% enriched fuel having 3-years life cycle. The spent fuel (SF) will be transferred into the spent fuel pool (SPF), where it stays for 8 years before being transferred to Russia. The SPF plays a crucial role during 8 years when the SP resides in there. This paper investigates the shielding of this structure as it is designed to shield the SF radiation. In this study, the SF isotope inventory, for different cycles and with different burnups, was calculated using WIMS/4D transport code. Using MCNP4C nuclear code, the intensity of γ rays was obtained in different layers of SFP shields. These layers include the water above fuel assemblies (FA) in pool, concrete wall of the pool and water laid above transferring fuels. Results show that γ rays leakage from the shield in the mentioned layers are in agreement with the plant's PSAR data. Finally we analyzed an accident were the water height above the FA in the pool drops to 47 cm. In this case it was observed that exposure dose above pool, 10 and 30 days from the accident, are still high and in the levels of 1000 and 758 R/hr.

  8. Black, White and Grey

    Directory of Open Access Journals (Sweden)

    Nasrin Nooshfar

    2011-05-01

    Full Text Available Background/Objective: Development of science and"nart achieved with saving independence, separation"nclassification and studying their details. The other hand"nis combination of these to create a new world with"nwide dimensions and take a place to human needs."nMaterials and Methods: Our attempt is to make"nhealth-care places pleasant and attractive for patients."nWe offer best services, but they are not comfortable"nand happy in these places. They are afraid of the staff,"nequipment and the environment. For this purpose"nwe mixed the brightness and darkness of radiologic"nimages with white and black photographs or paintings"ncomplementary to create analog artistic images that"ncould be converted to digital printing by DICOM"ninterfaces on hard copies."nConclusion: Fear, pictures a bad memory in the"npatient's mind forever. We mixed radiology and"nimaging with photography as a science and art mixture"nto conflict with these problems, it is more effective in"nchildren who are suffering from social and known"ndiseases and can not adapt themselves with their"nsituations. This could create a good memory between"nthe human body image and sentimental experience."nIn the literature, printed radiologic images were used"nas fine art on glass and paper, metal and flowers were"nemployed to mix.* *Wim Delvoye (born 1965 ,Wervik"nand Steven N.Meyers and Merille Raikes

  9. Analysis of Yearly Traffic Fluctuation on Latvian Highways

    Science.gov (United States)

    Freimanis, A.; Paeglı¯tis, A.

    2015-11-01

    Average annual daily traffic and average annual truck traffic are two most used metrics for road management decisions. They are calculated from data gathered by continuous counting stations embedded in road pavement, manual counting sessions or mobile counting devices. Last two usually do not last longer than a couple of weeks so the information gathered is influenced by yearly traffic fluctuations. Data containing a total of 8,186,871 vehicles or 1989 days from 4 WIM stations installed on highways in Latvia were used in this study. Each of the files was supposed to contain data from only 1 day and additional data were deleted. No other data cleaning steps were performed, which increased the number of vehicles as counting systems sometimes split vehicles into two. Weekly traffic and weekly truck traffic was normalized against respective average values. Each weekly value was then plotted against its number in a year for better visual perception. Weekly traffic amplitudes were used to assess differences between different locations and standard deviations for fluctuation comparison of truck and regular traffic at the same location. Results show that truck traffic fluctuates more than regular traffic during a year, especially around holidays. Differences between counting locations were larger for regular traffic than truck traffic. These results show that average annual daily traffic could be influenced more if short term counting results are adjusted by factors derived from unsuitable continuous counting stations, but truck traffic is more influenced by the time of year in which counting is done.

  10. Looking at our origins

    CERN Multimedia

    Nairucu Arts

    2011-01-01

    Exhibition by Nairucu-Arts, in collaboration with the Anthropology Museum Giuseppe Sergi, Università la Sapienza, Roma, Italy and ECOLINT, Campus des Nations. The exhibition comprises: posters (in English and French) intended for a large audience with text from Prof. Giorgio Manzi, Julia Rizzo, Fabio Di Vincenzo, illustrated with art drawings from Carlo Ranzi, Italy. The exhibition will also present drawings from the students of the Art Classes of Karin Bain and Fabien Bruttin at ECOLINT,Geneva. On 2nd March at 5 p.m. you will be welcomed with a drink before the conference that will be given in English at 6 p.m in the CERN Council Room by Wim De Geest, a retired Professor from KUB (Catholic University of Brussels). Title: There's no language like our language, like no language we know. But how did it evolve? A summary in French will be made available for the public. http://association.web.cern.ch/association/en/OtherActivities/Origins.html

  11. The European activation file EAF-4. Summary documentation

    Energy Technology Data Exchange (ETDEWEB)

    Kopeckey, J.; Nierop, D.

    1995-12-01

    This report describes the contents of the fourth version of the European Activation File (EAF-4), containing cross-sections for neutron induced reactions (0-20 MeV energy range) primarily for use in fusion-reactor technology. However, it can be used in other applications as well. The starter was the file EAF-3.1. The present version contains cross section data for all target nuclides which have half-lives longer than 0.5 days extended by actinides up to and including fermium (Z=100). Corss sections to isomeric states are listed separately and if the isomers live longer than 0.5 day they are also included as targets. The library includes 764 target nuclides with 13,096 reactions with non-zero cross-sections (>10{sup -8} b) below 20 MeV. The library is available in point-wise data and multigroup constant data in four different energy group structures (GAM-2, VITAMIN-J, WIMS and XMAS). A complementary uncertainty file has been gereated for all reactions in one-energy group structure for threshold reactions and three-groups for (n, {gamma}) and (n, f) reactions. The error estimates for this file are adopted either form experimental information or from systematics. (orig.).

  12. Drop Performance Test of CRDMs for JRTR

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Myoung-Hwan; Cho, Yeong-Garp; Chung, Jong-Ha [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Jung-Hyun [POSCO Plandtec Co. Ltd, Ulsan (Korea, Republic of); Lee, Kwan-Hee [RIST, Pohang (Korea, Republic of)

    2015-10-15

    The drop test results of CRDMs with AC-type electromagnet show that the initial delay times are not satisfied with the requirement, 0.15 seconds. After the replacement of the electromagnet from AC-type to DCtype, the drop times of CARs and accelerations due to the impact of moving parts are satisfied with all requirements. As a result, it is found that four CRDMs to be installed at site have a good drop performance, and meet all performance requirements. A control rod drive mechanism (CRDM) is a device to control the position of a control absorber rod (CAR) in the core by using a stepping motor which is commanded by the reactor regulating system (RRS) to control the reactivity during the normal operation of the reactor. The top-mounted CRDM driven by the stepping motor for Jordan Research and Training Reactor (JRTR) has been developed in KAERI. The CRDM for JRTR has been optimized by the design improvement based on that of the HANARO. It is necessary to verify the performances such as the stepping, drop, endurance, vibration, seismic and structural integrity for active components. Especially, the CAR drop curves are important data for the safety analysis. This paper describes the test results to demonstrate the drop performances of a prototype and 4 CRDMs to be installed at site. The tests are carried out at a test rig simulating the actual reactor's conditions.

  13. Study on the Internationalization of Korean Nuclear Journals

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Y. C.; Yoo, J. B. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    This paper is intended to provide some thoughts for a listing of the Korean nuclear journals in the Science Citation Index(SCI), by an analysis of indicators based on the data gathered from relevant literature : Journal of Korean Nuclear Society(JKNS) and Nuclear Engineering and Technology (NET) as cited in the SCI source journal. The study examines as an indicator the number of papers in the JKNS and NET that have been cited by KAERI researchers in the SCI Source Journal (to the end of August 2006). This paper also gives a review of the statistics provided by the Institute for Scientific Information (ISI), as an authoritative source for an evaluation of a global cataloguing of scientific and technical journals, and suggests a view for a listing of the Korean nuclear journals in the SCI by a review of associated selection criteria and methods. It concludes there is a need to increase the number of citations in the SCI source journals of the NET papers to be published from the most recent previous two years.

  14. Development of a MAAP-based Severe Accident Training Simulator using Visual System Analyzer

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Jae Seung [SENTECH, Daejeon (Korea, Republic of); Park, Soo Yong; Ahn, Kwang Il; Kim, Kyung Doo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-10-15

    The recent environment of severe accident analysis requires high performance computers to simulate complicated reactor and containment phenomena. In parallel with this, rapid advances in computer technology now enable these codes to run in real or almost real time. The remaining limitation restricting their use on an even wider scale is that most of the existing codes are still subject to a complicated I/O structure. Even user-friendly graphical user interfaces (GUI) will be not likely to help better and efficient interpretation of the analysis results obtained from these codes as well as for their increased use. This situation has motivated the development of easy-to-use GUI tools for severe accident codes, such as ViSA, SNAP, MAAP4-GRAAP, SATS, and et al. For instance, ViSA enables the thermal-hydraulic system codes to be used like a conventional nuclear plant analyzer. Recently, a project for a real time simulation of results obtained using MAAP4 codes under the ViSA environment has been initiated in KAERI. Such a GUI-based interactive interface can be very useful in sharing real time analysis results obtained from the MAAP code. The purpose of this paper is to introduce the current status of a MAAP-based Severe Accident Simulator being coupled with the ViSA system

  15. An Analysis of Station Blackout Sequences Using MELCOR1.8.5 Code for the Severe Accident Analysis DB

    Energy Technology Data Exchange (ETDEWEB)

    Song, Y. M.; Ahn, K. I. [KAERI, Daejeon (Korea, Republic of)

    2010-12-15

    The Korea Atomic Energy Research Institute (KAERI) has been constructing severe accident analysis database (DB) under a National Nuclear R and D Program. Especially, MAAP (commercial code being widely used for industries) DB for many scenarios including station blackout (SBO) has been completed up to now. This report shows the analysis results for SBO scenarios using MELCOR code. These results will be used for the degree of completion after being compared with MAAP results. The developing strategy of MELCOR code is the same with that of MAAP DB. For the generation of data set, the Korean standard nuclear power plant (KSNP) has been selected as a reference plant and the eight SBO scenarios are chosen to be analyzed based on the PSA results (these eight scenarios accounted for 99 percent of occurrence frequency of total 197 SBO scenarios). Both thermal hydraulics (T/H) and source term analysis have been performed using MELCOR version 1.8.5 for the chosen scenarios. But only major T/H variables treated in the MAAP report are listed among the generated data set, which shows the characteristics of each scenario. These SBO results together with those of the other initiating events (to be analyzed in the future) will be used as inputs for DB construction and special value will be found in the comparing and complimentary process with MAAP DB

  16. Present status of neutron beam facilities at the research reactor, HANARO, and its future prospect

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang-Hee; Kang, Young-Hwan; Kuk, Il-Hiun [Korea Atomic Energy Research Institute, Taejon (Korea)

    2001-03-01

    Korea has been operating its new research reactor, HANARO, since its first criticality in 1995. It is an open-tank-in-pool type reactor using LEU fuel with thermal neutron flux of 2 x 10{sup 14} nominally at the nose in the D{sub 2}O reflector having 7 horizontal beam ports and a provision of vertical hole for cold neutron source installation. KAERI has pursued an extensive instrument development program since 1992 by the support of the nuclear long-term development program of the government and there are now 4 working instruments. A high resolution powder diffractometer and a neutron radiography facility has been operational since late 1997 and 1996, respectively. A four-circle diffractometer has been fully working since mid 1999 and a small angle neutron spectrometer is just under commissioning phase. With the development of linear position sensitive detector with delay-line readout electronics, we have developed a residual stress instrument as an optional machine to the HRPD for last two years. Around early 1998 informal users program started with friendly users and it became a formal users support program by the ministry of science and technology. Short description for peer group formation and users activities is given. (author)

  17. Upgrade of The Cyber R and D Platform

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Chang Seong; Lee, Kyung Jong; Yang, Tae Chun; Kim, Tae Sung; Hong, Hyun Joo [Kyungsung Univ., Seoul (Korea, Republic of)

    2007-02-15

    Recently, it is necessary to demonstrate the program and experience the safety of radiation disposal by themselves. The objective of this research is to develop a cyber-based performance assessment program for the radiation disposal which is fit for Korean environment. This research covers the following four areas: - Development of Java-based MDPSA pre-processor - Linking MDPSA code to pre and post-processor. - Linking MDPSA code to Cyber R and D platform - Modification of the Cyber R and D platform. The results of this research can be used as a PR database for the central and local government. Using the web-based system, any person or interest group can plug in the system and experience the safety and clarity of the atomic energy and radiation disposal. Also, within the KAERI, research-related knowledge can be stored as a structured format. This enables the sharing, reusability, transparency, reliability and transferability of research results, and promotes the efficiency of research efforts within and outside of research team.

  18. Preliminary study of CANDU moderator thermal hydraulics using the CUPID code

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sang Gi; Jeong Jae Jun [Pusan National Univ., Busan (Korea, Republic of); Lee, Jae Ryong; Kim, Hyoung Tae [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    When the moderator cooling system fails, moderator may act as to remove decay heat which occurs in fuel. During loss of coolant accident (LOCA), the film boiling occurs in the Calandria tube (CT) because the hot pressure tube would deform into contacting with the calandria tube. And lower subcooling would decrease the margin of the CT to dryout. So, it is important to estimate a local subcooling of the moderator inside the Calandria vessel. However, in order to predict the internal temperature the study of empirical experiments and calculations are needed because only the inlet/outlet temperature can be measured in real reactor. In this study, the internal flow of the moderator was predicted by using the CUPID code, which has been developed in KAERI. The CUPID adopts three dimensional, transient, two phase and three field model, and includes various physical models and correlations of the interfacial mass, momentum and energy transfer for the closure relations of the two fluid model. The CUPID code shows single phase and two phase flow through two phase flow calculations of virtual can be applied.

  19. Replacement of Co-base alloy for radiation exposure reduction in the primary system of PWR

    Energy Technology Data Exchange (ETDEWEB)

    Han, Jeong Ho; Nyo, Kye Ho; Lee, Deok Hyun; Lim, Deok Jae; Ahn, Jin Keun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Kim, Sun Jin [Hanyang Univ., Seoul (Korea, Republic of)

    1996-01-01

    Of numerous Co-free alloys developed to replace Co-base stellite used in valve hardfacing material, two iron-base alloys of Armacor M and Tristelle 5183 and one nickel-base alloy of Nucalloy 488 were selected as candidate Co-free alloys, and Stellite 6 was also selected as a standard hardfacing material. These four alloys were welded on 316SS substrate using TIG welding method. The first corrosion test loop of KAERI simulating the water chemistry and operation condition of the primary system of PWR was designed and fabricated. Corrosion behaviors of the above four kinds of alloys were evaluated using this test loop under the condition of 300 deg C, 1500 psi. Microstructures of weldment of these alloys were observed to identify both matrix and secondary phase in each weldment. Hardnesses of weld deposit layer including HAZ and substrate were measured using micro-Vickers hardness tester. The status on the technology of Co-base alloy replacement in valve components was reviewed with respect to the classification of valves to be replaced, the development of Co-free alloys, the application of Co-free alloys and its experiences in foreign NPPs, and the Co reduction program in domestic NPPs and industries. 18 tabs., 20 figs., 22 refs. (Author).

  20. Cycle Average Peak Fuel Temperature Prediction Using CAPP/GAMMA+

    Energy Technology Data Exchange (ETDEWEB)

    Tak, Nam-il; Lee, Hyun Chul; Lim, Hong Sik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    In order to obtain a cycle average maximum fuel temperature without rigorous efforts, a neutronics/thermo-fluid coupled calculation is needed with depletion capability. Recently, a CAPP/GAMMA+ coupled code system has been developed and the initial core of PMR200 was analyzed using the CAPP/GAMMA+ code system. The GAMMA+ code is a system thermo-fluid analysis code and the CAPP code is a neutronics code. The General Atomics proposed that the design limit of the fuel temperature under normal operating conditions should be a cycle-averaged maximum value. Nonetheless, the existing works of Korea Atomic Energy Research Institute (KAERI) only calculated the maximum fuel temperature at a fixed time point, e.g., the beginning of cycle (BOC) just because the calculation capability was not ready for a cycle average value. In this work, a cycle average maximum fuel temperature has been calculated using CAPP/GAMMA+ code system for the equilibrium core of PMR200. The CAPP/GAMMA+ coupled calculation was carried out for the equilibrium core of PMR 200 from BOC to EOC to obtain a cycle average peak fuel temperature. The peak fuel temperature was predicted to be 1372 .deg. C near MOC. However, the cycle average peak fuel temperature was calculated as 1181 .deg. C, which is below the design target of 1250 .deg. C.

  1. Magnetic Actuation Connector Between Extension Shaft and Armature for Bottom Mounted Control Rod Drive Mechanism

    Energy Technology Data Exchange (ETDEWEB)

    Huh, Hyung; Cho, Yeong Garp; Kim, Jong In [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The electromagnet and armature inside the guide tube interact and produce magnetism, thus making the armature, connecting extension shaft and control rod move up and down to control the power of reactor. During the overhaul, the control absorber rod (CAR), extension shaft, and armature of BMCRDM are lifted together for closing a seal valve. But total length of CAR assembly is so long that it cannot be lifted due to exposure above the water level of pool which is strictly controlled. In addition to this, it is difficult to calibrate a position indicator and lifting force of electromagnet without armature assembly as a seal valve is closed. For this reason, it is necessary to install a disconnecting system between armature and extension shaft. Therefore, KAERI has developed magnetic actuation connector using plunger between armature and extension shaft for the bottom mounted control rod drive mechanism in research reactor. The results of a FEM and the experiments in this work lead to the following conclusions: The FEM result for the design of the magnetic actuation connector is compared with the measured lifting force of prototype production. As a result, it is shown that the lifting force of the prototype connector has a good agreement with the result of the FEM. A newly developed technique of prototype magnetic actuation connector which is designed by FEM analysis result is proposed.

  2. Development of a Base Model for the New Fire PSA Training

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kilyoo; Kang, Daeil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Wee Kyong; Do, Kyu Sik [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-05-15

    US NRC/EPRI issued a new fire PSA method represented by NUREG/CR 6850, and have been training many operators and inspectors to widely spread the new method. However, there is a limitation in time and efficiency for many foreigners, who generally have communication problem, to participate in the EPRI/NRC training to learn the new method. Since it is about time to introduce the new fire PSA method as a regulatory requirement for the fire protection in Korea, a simple and easy-understandable base model for the fire PSA training is required, and KAERI-KINS is jointly preparing the base model for the new fire PSA training. This paper describes how the base model is developed. Using an imaginary simple NPP, a base model of fire PSA following the new fire PSA method was developed in two ways from the internal PSA model. Since we have the base model and know the process of making the fire PSA model, the training for the new fire PSA method can be in detail performed in Korea.

  3. Basic Design of Experimental Facility for Measuring Pressure Drop of IHX in a SFR

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Yung-Joo; Eoh, Jae-Hyuk; Kim, Hyungmo; Lee, Dong-Won; Jeong, Ji-Young; Lee, Hyeong-Yeon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Dong Eok [Kyungpook National Univ., Daegu (Korea, Republic of)

    2015-05-15

    The conceptual design of the Prototype gen-IV SFR (PGSFR) with a 150 MWe capacity was commenced in 2012 through the national long-term R and D program by KAERI. Then, PGSFR is now being designed with the defense in depth concept with active, passive and inherent safety features to acquire design approval for PGSFR from the Korean regulatory authority by 2020. PGSFR is a sodium-cooled pool-type fast reactor with all primary components including the primary heat transport system (PHTS) pumps and IHXs are located inside a sodium pool. The heat produced due to fission in the core is transported by primary sodium to secondary sodium in a sodium to sodium intermediate heat exchanger (IHX), which in turn is transferred to water in a steam generator (SG). Basic design of the IHX flow characteristic test facility, WEIPA was conducted based on the three-level scaling methodology in order to preserve the flow characteristics of the IHX in PGSFR. This test facility is intended to measure a high precision pressure drop at the shell-side of the IHX. This paper describes the aspects of the current design features of the IHX in PGSFR, scaling and basic design features of the facility.

  4. Comparison Between helium cycle and Supercritical CO{sub 2} Cycle for MMR and AMR

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Seong Jun; Lee, Jeong Ik; Ahn, Yoon Han; Lee, Je Kyoung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2013-05-15

    Korea Atomic Energy Research Institute (KAERI) started the development of Mobile Multi-Purpose Reactor (MMR), which is a 10MWth gas-cooled reactor. MMR is aiming for maximizing mobility, high performance, durability and safety. This is in order to use the MMR for many purposes such as ship propulsion, train engine and so on. MMR generally uses helium Brayton cycle as a power conversion system since it can obtain very simple system arrangement with direct cycle. However, some researchers have proposed that the supercritical carbon dioxide (S-CO{sub 2}) Brayton cycle can be more efficient energy converting cycle for the high temperature gas cooled reactor (HTGR) and the very high temperature reactor (VHTR) system as well. Thus, this paper is to compare helium Brayton cycle to the S-CO{sub 2} Brayton cycle in terms of the efficiency while varying turbine inlet temperature (T. I. T). A cascaded S-CO{sub 2} cycle which had been proposed by Argonne National laboratory (ANL) was used as the S-CO{sub 2} Brayton cycle configuration. This cycle is to overcome the mismatch of temperature drop between reactor coolant and CO{sub 2} through the reactor heat exchanger (RHX). Our research team reviewed the ANL research by using the in-house codes developed by the Korea Advanced institute of Science and Technology (KAIST) research team. The calculation error between the in-house code and previous result was -0.36%.

  5. PWR core stablity aganst xenon-induced spatial power oscillation

    Energy Technology Data Exchange (ETDEWEB)

    Moon, H.J.; Han, K.I. (Korea Advanced Energy Research Inst., Seoul (Republic of Korea))

    1982-06-01

    Stability of a PWR core against xenon-induced axial power oscillation is studied using one-dimensional xenon transient analysis code, DD1D, that has been developed and verified at KAERI. Analyzed by DD1D utilizing the Kori Unit 1 design and operating data is the sensitivity of axial stability in a PWR core to the changes in core physical parameters including core power level, moderator temperature coefficient, core inlet temperature, doppler power coefficient and core average burnup. Through the sensitivity study the Kori Unit 1 core is found to be stable against axial xenon oscillation at the beginning of cycle 1. But, it becomes less stable as burnup progresses, and unstable at the end of cycle. Such a decrease in stability is mainly due to combined effect of changes in axial power distribution, moderator temperature coefficient and doppler power coefficient as core burnup progresses. It is concluded from the stability analysis of the Kori Unit 1 core that design of a large PWR with high power density and increased dimension can not avoid xenon-induced axial power instabilites to some extents, especially at the end of cycle.

  6. Feasibility study on production of Co-60 in PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Park, Kyung Bae; Han, Hyon Soo; Joo, Po Kook

    2000-05-01

    The purpose of this study is to analyze the safeties and the economics for Co-60 production from Wolsung PHWR and to verify the feasibility on the manufacturing of the final Co-60 source for industrial irradiation. The feasibility of reactor conversion was carried out with KEPCO collaboration. Through the site survey on the experience of Gentililly-2 in Canada, a feasibility of plant conversion, changes in design, equipment and tools for Co-60 production was verified. It was estimated that the reactor conversion would not impose adverse impact on plant safety. For the encapsulation of radiation source and storage of the final products, a modification of concrete hot cell at KAERI was primary concerns. The installation and improvement of facilities are needed to avoid cross contamination and extra radiation exposure. Main items for these are pressure gauge, separated HEPA filter the ceiling separation, extra-shielding and ceiling hoist system. At present, storage pool has got admission based on 400 kCi. But it is necessary to seismic analysis and design improvement of shielding to store 10 MCi (Co-60) which is the estimated Co-60 capacity produced by 3 PHWRs. According to present investigation, a production of Co-60 by PHWR and RIPE was seemed to be an economically feasible business and it was also expected that a joint venture will be able to realize by cooperation with MDS Nordion Co.

  7. Study on the AMO data production and evaluation techniques

    Energy Technology Data Exchange (ETDEWEB)

    Rhee, Yong Joo; Yoo, B. D.; Choe, A. S.; Han, J. M.; Jung, E. C.; Rho, S. P.; Yi, J. H.; Jeong, D. Y.; Lee, K. S.; Park, H. M.; Kim, S. K.; Song, K. S.; Lee, J. M

    1998-01-01

    AMODS (Atomic, Molecular, and Optical Database System) which can be accessed with the URL http://amods.kaeri.re.kr consists of a computer system which is an Alpha workstation 600 with UNIX O/S and the APACHE 1.2 WWW server installed on an independently mounted file system of 4.3 GB. Currently the data in AMODS is mostly atom-related and consists of atomic spectral lines, atomic transition probabilities, atomic energy levels, atomic transition lines, and CODATA 86 as well as several reference data. Meanwhile spectroscopic parameter of Sm which is one of the rare earth elements, has been measured, resulting in production of 36 isotope shift data of the high-lying even parity states, followed by the measurement of autoionization states. New 31 autoionization states are found and energy levels of them are measured. The Fano`s q parameters are determined through the theoretical analysis of the experimental data. (author). 11 refs., 3 tabs., 15 figs

  8. Development of fission Mo-99 production technology

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jin Ho; Choung, W. M.; Lee, K. I. and others

    2001-05-01

    This R and D project is planed to supply domestic demands of Mo-99 through fission route, and consequently this project will be expected to rise up utilization of HANARO and KAERI's capability for marketing extension into domestic and oversea radiopharmaceutical market. HEU and LEU target types are decided and designed for fission Mo-99 production in domestic. Experimental study of target fabrication technology was performed and developed processing equipments. And conceptual design of target loading/unloading in/from HANARO device are performed. Tracer test of Mo-99 separation and purification process was performed, test results reach to Mo-99 recovery yield above 80% and decontamination factor above 1600. Combined Mo-99 separation and purification process was decided for hot test scheduled from next year, and performance test was performed. Conceptual design for modification of existing hot cell for fission Mo-99 production facility was performed and will be used for detail design. Assumption for the comparison of LEU and HEU target in fission Mo-99 production process were suggested and compared of merits and demerits in view of fabrication technology and economy feasibility.

  9. Control and Data Acquisition System of the ATLAS Facility

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ki-Yong; Kwon, Tae-Soon; Cho, Seok; Park, Hyun-Sik; Baek, Won-Pil; Kim, Jung-Taek

    2007-02-15

    This report describes the control and data acquisition system of an integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) facility, which recently has been constructed at KAERI (Korea Atomic Energy Research Institute). The control and data acquisition system of the ATLAS is established with the hybrid distributed control system (DCS) by RTP corp. The ARIDES system on a LINUX platform which is provided by BNF Technology Inc. is used for a control software. The IO signals consists of 1995 channels and they are processed at 10Hz. The Human-Machine-Interface (HMI) consists of 43 processing windows and they are classified according to fluid system. All control devices can be controlled by manual, auto, sequence, group, and table control methods. The monitoring system can display the real time trend or historical data of the selected IO signals on LCD monitors in a graphical form. The data logging system can be started or stopped by operator and the logging frequency can be selected among 0.5, 1, 2, 10Hz. The fluid system of the ATLAS facility consists of several systems including a primary system to auxiliary system. Each fluid system has a control similarity to the prototype plant, APR1400/OPR1000.

  10. Development of dual cooled annular fuel and its possibility to enhance both economy and safety of light water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Yanghyun; Kim, Keonsik; Park, Jeongyong; Yang, Yongsik; Kim, Hyungkyu; In, Wangkee; Song, Kunwoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-03-15

    Over the past few decades, extensive studies have been performed to improve the reliability and safety of light water reactor (LWR) fuel. In recent years, power updating of about 10% is being achieved by modifying safety analysis methodology and subsequent increase in safety margin. But departure from nucleate boiling (DNB) and loss of coolant accident (LOCA) are still two of the most important limiting factors which would restrict power updating more than 10%. Duel cooled annular fuel, cooled in both internal and external cooling channel, has advantages of considerably lower heat flux and lower fuel temperature than conventional solid fuel. While lower heat flus gives higher DNB margin for the same power retie, lower temperature reduces the stored energy of fuel. However, there are many technical issues that should be addressed before any new type of fuel can be considered for application to LWR. This paper describes the key technologies that Korea Atomic Energy Research Institute (KAERI) has developed for dual cooled annular fuel and discusses the feasibility of its application to LWR.

  11. Analysis of once-through steam generator instability

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Han Ok; Kang, Hyung Suk; Cho, Bong Hyun; Yoon, Ju Hyeon [Korea Atomic Energy Research Institute, Taejon (Korea)

    1998-03-01

    KAERI is carrying out a development of the design for a new type of integral reactor named SMART (System-integrated Modular Advanced Reactor). Two models, the frequency domain-linear model and the time domain-nonlinear model, are developed for the analysis of once-through helical steam generator flow instability. The linear model is used for easy determination of critical point with constant heat flux condition. The nonlinear model is for the analysis of oscillation characteristics beyond the critical point as well as determination of the point with real primary boundary conditions. The developed linear model is utilized to evaluate the effect of several nondimensional parameters on flow stability for the wide range of input conditions. The results from the developed nonlinear model are compared with the existing experimental data including steady state values and critical conditions. The calculated lengths of each region and pressure drops in the steady show almost same trends with Nariai's experimental results. Two developed models can be utilized to analyze the steam generator flow instabilities and to design the inlet orifices are to prevent flow instabilities. (author). 118 refs., 32 figs., 1 tab.

  12. Human-Machine interface for off normal and emergency situations in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-01-01

    Many nuclear power plants (NPPs) have reported that a high percentage of all major failures in the plants are caused by human errors. Therefore, there has been much focus on elimination of human errors, enhancement of human performance, and general improvement of human machine interface (HMI). Both the utility management and the regulators are demanding improvement in this area. The International Atomic Energy Agency (IAEA) Specialists' Meeting on 'Human-Machine Interface for Off Normal and Emergency Situations in Nuclear Power Plants' was co-organized by the Korea Atomic Energy Research Institute (KAERI) and the Korea Power Engineering Company, INC (KOPEC), and took place in Taejeon, Republic of Korea, 1999 October 26-28. Fifty eight participants, representing nine member countries reviewed recent developments and discussed directions for future efforts in the Human-Machine Interface for Off Normal and Emergency Situations in NPPs. Twenty papers were presented, covering a wide spectrum of technical and scientific subjects including recent experience and benefits from Operational Experience with HMI, Development of HMI System, Licensing Issues for HMI and Future Development and Trends. (Author)

  13. Study on the establishment of the IAEA Asian Network for Education in Nuclear Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Lee, H. Y. [and others

    2005-05-01

    The purpose of this project is to establish a web-portal including a database for the exchange of information and materials for nuclear education and training among ANENT members, and eventually contribute to the sustainable development of nuclear technology for peaceful uses in the Asian IAEA member countries. The project has resulted in the development of a web-portal for ANENT (www.anent-iaea.org). The portal primarily includes a Database for Nuclear Education and Training (NET DB). and functions to deal with group activities which were identified in the first ANENT Coordination Committee meeting. NET DB contains information about relevant education and training institutions/universities in terms of their faculty members or researchers, curricula, education and training materials, etc. While, the group activities are exchange of information and materials for education and training, e-learning, establishment of a reference curricula and a system for a mutual recognition of credits, and cooperation with other networks. Finally, an IAEA regional workshop was held to review the developed web-portal and an agreement was reached on the use of the web-portal with some revisions. Furthermore, the IAEA has requested the NTC/KAERI to develop ANENT Cyber-Platform for the continued upgrading of ANENT Web-portal.

  14. Major Achievements and Prospect of the ATLAS Integral Effect Tests

    Directory of Open Access Journals (Sweden)

    Ki-Yong Choi

    2012-01-01

    Full Text Available A large-scale thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation, has been operated by KAERI. The reference plant of ATLAS is the APR1400 (Advanced Power Reactor, 1400 MWe. Since 2007, an extensive series of experimental works were successfully carried out, including large break loss of coolant accident tests, small break loss of coolant accident tests at various break locations, steam generator tube rupture tests, feed line break tests, and steam line break tests. These tests contributed toward an understanding of the unique thermal-hydraulic behavior, resolving the safety-related concerns and providing validation data for evaluation of the safety analysis codes and methodology for the advanced pressurized water reactor, APR1400. Major discoveries and lessons found in the past integral effect tests are summarized in this paper. As the demand for integral effect tests is on the rise due to the active national nuclear R&D program in Korea, the future prospects of the application of the ATLAS facility are also discussed.

  15. Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea

    Directory of Open Access Journals (Sweden)

    Yeong-il Kim

    2013-01-01

    Full Text Available Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for electricity generation, because it can utilize efficiently uranium resources and reduce radioactive waste. Acknowledging the importance of a fast reactor in a future energy policy, the long-term advanced SFR development plan was authorized by KAEC in 2008 and updated in 2011 which will be carried out toward the construction of an advanced SFR prototype plant by 2028. Based upon the experiences gained during the development of the conceptual designs for KALIMER, KAERI recently developed advanced sodium-cooled fast reactor (SFR design concepts of TRU burner that can better meet the generation IV technology goals. The current status of nuclear power and SFR design technology development program in Korea will be discussed. The developments of design concepts including core, fuel, fluid system, mechanical structure, and safety evaluation have been performed. In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities.

  16. Fabrication and integrity test preparation of HIP-joined W and ferritic-martensitic steel mockups for fusion reactor development

    Science.gov (United States)

    Lee, Dong Won; Shin, Kyu In; Kim, Suk Kwon; Jin, Hyung Gon; Lee, Eo Hwak; Yoon, Jae Sung; Choi, Bo Guen; Moon, Se Youn; Hong, Bong Guen

    2014-10-01

    Tungsten (W) and ferritic-martensitic steel (FMS) as armor and structural materials, respectively, are the major candidates for plasma-facing components (PFCs) such as the blanket first wall (BFW) and the divertor, in a fusion reactor. In the present study, three W/FMS mockups were successfully fabricated using a hot isostatic pressing (HIP, 900 °C, 100 MPa, 1.5 hrs) with a following post-HIP heat treatment (PHHT, tempering, 750 °C, 70 MPa, 2 hrs), and the W/FMS joining method was developed based on the ITER BFW and the test blanket module (TBM) development project from 2004 to the present. Using a 10-MHz-frequency flat-type probe to ultrasonically test of the joint, we found no defects in the fabricated mockups. For confirmation of the joint integrity, a high heat flux test will be performed up to the thermal lifetime of the mockup under the proper test conditions. These conditions were determined through a preliminary analysis with conventional codes such as ANSYS-CFX for thermal-hydraulic conditions considering the test facility, the Korea heat load test facility with an electron beam (KoHLT-EB), and its water coolant system at the Korea Atomic Energy Research Institute (KAERI).

  17. Commissioning of the ATLAS thermal-hydraulic integral test facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeon-Sik [Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)], E-mail: yskim3@kaeri.re.kr; Choi, Ki-Yong; Park, Hyeon-Sik; Cho, Seok; Kim, Bok-Deug; Choi, Nam-Hyeon; Baek, Won-Pil [Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

    2008-10-15

    KAERI recently constructed a new thermal-hydraulic integral test facility for advanced pressurized water reactors (PWRs) - ATLAS. The ATLAS facility has the following characteristics: (a) 1/2-height and length, 1/288-volume, and full pressure simulation of APR1400, (b) maintaining a geometrical similarity with APR1400 including 2(hot legs) x 4(cold legs) reactor coolant loops, direct vessel injection (DVI) of emergency core cooling water, integrated annular downcomer, etc., (c) incorporation of specific design characteristics of OPR1000 such as cold leg injection and low-pressure safety injection pumps, (d) maximum 10% of the scaled nominal core power. The ATLAS will mainly be used to simulate various accident and transient scenarios for evolutionary PWRs, OPR1000 and APR1400: the simulation capability of broad scenarios including the reflood phase of a large-break loss-of-coolant accident (LOCA), small-break LOCA scenarios including DVI line breaks, a steam generator tube rupture, a main steam line break, a feed line break, a mid-loop operation, etc. The ATLAS is now in operation after an extensive series of commissioning tests in 2006.

  18. Analysis report of the thermal-hydraulic characteristics of the high temperature/high pressure thermal-hydraulic test facility (VISTA) in steady state conditions

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Sik; Choi, Ki Yong; Cho, Seok; Lee, Sung Jae; Song, Chul Hwa; Park, Chun Kyong; Chung, Moon Ki

    2004-01-01

    The VISTA (Experimental Verification by Integral Simulation of Transients and Accidents) is an experimental facility to verify the performance and safety issues of the SMART-P (Pilot plant of the system-integrated modular advanced reactor). The basic design of the SMART-P has been completed by KAERI. The present report describes the experimental results on the water inventory distribution, the pressure distribution, and the differential pressure characteristics of the VISTA facility and on the heat transfer characteristics of the core simulating heater and the steam generator of the VISTA facility. There were little differences of their water inventories between the designed and the measured data. The pressure of the VISTA primary system kept near the steady-state operating pressure of 147 bar, and the differential pressures through the primary and secondary systems increased with the increase of their flow rates. Also the surface temperatures of core simulating heaters were measured, and the overall heat transfer coefficient of the VISTA steam generator was calculated to show a little higher values than that of the SMART-P.

  19. Experiments on Performance Sensitivity of SMART PRHRS using the High Temperature/High Pressure Thermal-Hydraulic Test Facility (VISTA)

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Sik; Choi, Ki Yong; Cho, Seok; Lee, Sung Jae; Choi, Nam Hyun; Min, Kyong Ho; Song, Chul Hwa; Park, Chun Kyong; Chung, Moon Ki

    2005-07-15

    The VISTA (Experimental Verification by Integral Simulation of Transients and Accidents) is an experimental facility to verify the performance and safety issues of the SMART-P (Pilot plant of the System-integrated Modular Advanced Reactor). The basic design of the SMART-P has been completed by KAERI. The present report describes the experimental results on the overall performance sensitivity of SMART PRHRS. During the reference test a stable flow occurs in a natural circulation loop which is composed of a steam generator secondary side, a secondary system, and a PRHRS, and it is ascertained by a repetition test. When the bypass valves of PRHRS are operated earlier than the isolation valves of secondary system, the primary system is effectively cooled but the inventory of PRHRS compensation tank is drained earlier. When the bypass valves of PRHRS are operated later than the isolation valves of secondary system, the primary system is not cooled. As the initial level of compensation tank is lowered to 16% of the full level, the steady natural circulation stops around 500 seconds. When the initial pressure of PRHRS is at 0.1 MPa, the natural circulation is not performed properly. When they are 2.5 and 3.5 MPa, it shows better performance than the reference test. Also when the isolation valve connecting the compensation tank is operated simultaneously with the PRHRS isolation valves, the primary system is more efficiently cooled but the inventory of PRHRS compensation tank is drained earlier.

  20. Simulation of the Passive Condensation Cooling Tank of the PASCAL Test Facility using the Component Thermal-hydraulic Analysis Code CUPID

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Hyoung Kyu; Lee, Seung Jun; Yoon, Han Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    The need for a multi-dimensional analysis of transient thermal hydraulic phenomena in a component of a nuclear reactor is increasing with the advanced design features, such as a direct vessel injection system, a gravity-driven safety injection system, and a passive cooling system. Motivated by this, the development of a new thermal-hydraulic analysis code, named CUPID, is in progress at KAERI (Korea Atomic Energy Research Institute). Its numerical solver and two-phase flow models have been verified against standard conceptual problems of single and two-phase flows and validated for thermal-hydraulic experiments in our previous studies. The simulation of the passive secondary cooling system, PAFS (Passive Auxiliary Feedwater System) has been considered as one of the practical applications of CUPID. In the present study, the PCCT (Passive Condensation Cooling Tank) of the PASCAL test facility was analyzed with CUPID prior to simulating the prototype PAFS system. The objectives of the PASCAL simulation were to validate physical models of CUPID and its applicability to the PAFS analysis. This paper presents the two-dimensional transient calculation results and the comparisons with the experimental data

  1. Experimental studies on dynamic system characteristics of the high temperature/high pressure thermal-hydraulic test facility(VISTA) for the power variation

    Energy Technology Data Exchange (ETDEWEB)

    Choi, K. Y.; Park, H. S.; Joe, S.; Park, C. K.; Lee, S. J.; Song, C. W.; Jeong, M. K. [KAERI, Taejon (Korea, Republic of)

    2003-10-01

    Dynamic system characteristics tests were carried out for the power variation by using the high temperature/high pressure thermal-hydraulic test facility, VISTA(Experimental Verification by Integral Simulation of Transient and Accidents), which had been constructed to simulate the SMART-P by KAERI. Experimental tests have been performed to investigate the thermal-hydraulic dynamic characteristics of the primary and the secondary systems in the range of 5% to 85% power. Automatic PID control logics were developed and installed to the VISTA facility to control the major thermal hydraulic parameters. Power was changed with either a step or a ramp changing method from the reference power of 10%, 25%, 50% and 75% to 5% or 10% higher power. It was found that there is no noticeable difference in the responses between a step and a ramp changing method. When unique constants of P, I, and D were used in the range of 5% to 85% power, it was found to be liable to lose the system control. Further studies are required to quantify the controllability and the time constants of the major thermal hydraulic parameters.

  2. Experiments for heat transfer characteristics and natural circulation performance of PRHRS of the high temperature/high pressure thermal-hydraulic test facility(VISTA)

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Sik; Choi, Ki Yong; Cho, Seok; Lee, Sung Jae; Song, Chul Hwa; Park, Chun Kyong; Chung, Moon Ki

    2004-01-01

    The VISTA (Experimental Verification by Integral Simulation of Transients and Accidents) is an experimental facility to verify the performance and safety issues of the SMART-P (Pilot plant of the System-integrated Modular Advanced Reactor). The basic design of the SMART-P has been completed by KAERI. The present report describes the experimental results on the heat transfer characteristics and the natural circulation performance of the PRHRS of the VISTA facility. A stable flow occurs in a natural circulation loop which is composed of a steam generator secondary side, a secondary system, and a PRHRS, and its flow rate corresponds to 12% of the rated feedwater flowrate of the secondary system. The heat transfers through the PRHRS heat exchanger and the emergency cooldown tank are sufficient enough to enable stable natural circulation. In the primary loop the natural circulation occurs due to the core decay heat and the heat removal of the steam generator. Although the flow rate in the primary loop fluctuates a little, the decay heat is removed easily.

  3. Experiments on Component Effects for Performance of SMART PRHRS using the High Temperature/High Pressure Thermal-Hydraulic Test Facility (VISTA)

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Sik; Choi, Ki Yong; Cho, Seok; Lee, Sung Jae; Choi, Nam Hyun; Min, Kyong Ho; Song, Chul Hwa; Park, Chun Kyong; Chung, Moon Ki

    2005-07-15

    The VISTA (Experimental Verification by Integral Simulation of Transients and Accidents) is an experimental facility to verify the performance and safety issues of the SMART-P (Pilot plant of the System-integrated Modular Advanced Reactor). The basic design of the SMART-P has been completed by KAERI. The present report describes the experimental results on the effects of several components for the performance of SMART PRHRS. Four experiments are performed separately without gas cylinder system, without PRHRS compensation tank, without initial filling of PRHRS loop, and without heat loss compensation of primary system. For all four cases a stable flow occurs in a natural circulation loop which is composed of a steam generator secondary side, a secondary system, and a PRHRS, which shows the similar trend of the reference case. Especially for cases without gas cylinder system and without initial filling of PRHRS loop the unsteady flow instability, which is occurred during the reference test, does not occur. The experimental results show that the overall performance of PRHRS is enhanced without PRHRS compensation tank, without initial filling of PRHRS loop, and without heat loss compensation.

  4. Design Evaluation of a Piping System in the SELFA Sodium Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Son, Seok-Kwon; Jo, Young-Chul; Lee, Hyeong-Yeon; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    In this study, design evaluations on the SELFA piping system has been conducted according to the ASME B31.1 and RCC-MRx RD-3600. The conservatism of the two codes was quantified based on the evaluation results. It was shown that B31.1 was more conservative for the sustained loads while less conservative for thermal expansion loads when compare with those of RD-3600. However, all the evaluation results according to the two codes were within the code allowables. There are two main piping systems in the SELFA test loop. In this study, the integrity of the SELFA piping system has been evaluated according to the two design-by-rule (DBR) codes of ASME B31.1 and RCC-MRx RD-3600. B31.1 is an industry design code for power piping while RD-3600 is a class 3 nuclear DBR code. The conservatism of the two codes was quantified based on the evaluation results as per the two DBR codes. The sodium test facility of the SELFA is under construction at KAERI for the investigation of thermo-hydraulic behavior of finned-tube sodium-to-air heat exchanger.

  5. Steady state thermal hydraulic analysis of LMR core using COBRA-K code

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eui Kwang; Kim, Young Gyun; Kim Young In; Kim Young Cheol

    1997-02-01

    A thermal hydraulics analysis code COBRA-K is being developed by the KAERI LMR core design technology development team. COBRA-K is a part of the integrated computation system for LMR core design and analysis, the K-CORE system. COBRA-K is supposed to predict the flow and temperature distributions in LMR core. COBRA-K is an extension of the previously published COBRA-IV-I code with several functional improvements. Specially COBRA-K has been improved to analyze single and multi-assembly, and whole-core in the transient condition. This report describes the overall features of COBRA-K and gives general input descriptions. The 19 pin assembly experimental data of ORNL were used to verify the accuracy of this code for the steady state analysis. The comparative results show good agreements between the calculated and the measured data. And COBRA-K can be used to predict flow and temperature distributions for the LMR core design. (author). 7 refs., 6 tabs., 13 figs.

  6. Development of superconducting acceleration cavity technology for free electron lasers

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Lee, Byung Cheol; Kim, Sun Kook; Jeong, Young Uk; Cho, Sung Oh

    2000-10-01

    As a result of the cooperative research between the KAERI and Peking University, the key technologies of superconducting acceleration cavity and photoelectron gun have been developed for the application to high power free electron lasers. A 1.5-GHz, 1-cell superconducting RF cavity has been designed and fabricated by using pure Nb sheets. The unloaded Q values of the fabricated superconducting cavity has been measured to be 2x10{sup 9} at 2.5K, and 8x10{sup 9} at 1.8K. The maximum acceleration gradient achieved was 12 MeV/m at 2.5K, and 20MV/m at 1.8 K. A cryostat for the 1-cell superconducting cavity has been designed. As a source of electron beam, a DC photocathode electron gun has been designed and fabricated, which is composed of a photocathode evaporation chamber and a 100-keV acceleration chamber. The efficiency of the Cs2Te photocathode is 3% nominally at room temperature, 10% at 290 deg C. The superconducting photoelectron gun system developed has been estimated to be a good source of high-brightness electron beam for high-power free electron lasers.

  7. Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

  8. Theoretical study of a waveguide THz free electron laser and comparisons with simulations

    Science.gov (United States)

    Shobuda, Yoshihiro; Chin, Yong Ho

    2016-09-01

    In a so-called waveguide free electron laser (FEL) for THz radiations, an extremely small aperture (˜mm ) waveguide is used to confine angularly wide spread radiation fields from a low energy electron beam into a small area. This confinement increases the interaction between the electron beam and the radiation fields to achieve a much higher FEL gain. The radiation fields propagate inside the waveguide as waveguide modes, not like a light flux in a free space FEL. This characteristic behavior of the radiation fields makes intuitive understanding of the waveguide FEL difficult. We developed a three-dimensional waveguide FEL theory to calculate a gain of THz waveguide FEL including the effects of the energy spread, the beam size and the betatron oscillations of an electron beam, and effects of a rectangular waveguide. The FEL gain can be calculated as a function of frequency by solving the dispersion relation. Theoretical gains are compared with simulation results for a waveguide FEL with a planar undulator similar to the KAERI one. Good agreements are obtained.

  9. Design of BPM PU for Low-Beta Proton Beam Using Magic Code

    CERN Document Server

    Park, S J; Bae, Y S; Hwang, W H; Huang, J Y; Nam, S H

    2003-01-01

    We have designed the BPM PU based on capacitive buttons for use in the KOMAC (Korea Multi-purpose Accelerator Complex), the high-intensity proton linac that are under development at the KAERI (Korea Atomic Research Institute), Korea. The KOMAC is aiming to produce CW 20 mA beam current at the 100 MeV energy. We have chosen the button-type PU since it is easier to fabricate than other type PUs including the stripline, and it could provide enough signal power because of the high beam current. The PU sensitivity was calculated by the MAGIC that is a kind of the Particle-In-Cell code that originates from the plasma science community. The utilization of the MAGIC code is especially useful for BPM PUs in the low-beta sections of the accelerator, because it is difficult to obtain the PU sensitivity experimentally due to the difficulties in simulating the low-beta beams by the electromagnetic waves in a test bench. In this presentation, we report on the design of the BPM PU based on the MAGIC calculation.

  10. In-vessel Retention Strategy for High Power Reactors - K-INERI Final Report (includes SBLB Test Results for Task 3 on External Reactor Vessel Cooling (ERVC) Boiling Data and CHF Enhancement Correlations)

    Energy Technology Data Exchange (ETDEWEB)

    F. B. Cheung; J. Yang; M. B. Dizon; J. Rempe

    2005-01-01

    In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe PWR (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for IVR, resulted in the U.S. Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing LWRs. However, it is not clear that currently proposed external reactor vessel cooling (ERVC) without additional enhancements could provide sufficient heat removal for higher-power reactors (up to 1500 MWe). Hence, a collaborative, three-year, U.S. - Korean International Nuclear Energy Research Initiative (INERI) project was completed in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) investigated the performance of ERVC and an in-vessel core catcher (IVCC) to determine if IVR is feasible for reactors up to 1500 MWe.

  11. Sodium fast reactor safety and licensing research plan. Volume II.

    Energy Technology Data Exchange (ETDEWEB)

    Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

    2012-05-01

    Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

  12. Evaluation of ductile-brittle transition behavior with neutron irradiation in nuclear reactor pressure vessel steels using small punch test

    Energy Technology Data Exchange (ETDEWEB)

    Kim, M. C.; Lee, B. S. [KAERI, Taejon (Korea, Republic of); Oh, Y. J. [Hanbat National Univ., Taejon (Korea, Republic of)

    2003-10-01

    A Small Punch (SP) test was performed to evaluate the ductile-brittle transition temperature before and after neutron irradiation in Reactor Pressure Vessel (RPV) steels produced by different manufacturing (refining) processes. The results were compared to the standard transition temperature shifts from the Charpy test and Master Curve fracture toughness test in accordance with the ASTM standard E1921. The samples were taken from 1/4t location of the vessel thickness and machined into a 10x10x0.5mm dimension. Irradiation of the samples was carried out in the research reactor at KAERI (HANARO) at about 290 .deg. C of the different fluence levels respectively. SP tests were performed in the temperature range of RT to -196 .deg. C using a 2.4mm diameter ball. For the materials before and after irradiation, SP transition temperatures (T{sub sp}), which are determined at the middle of the upper and lower SP energies, showed a linear correlation with the Charpy index temperature, T{sub 41J}. T{sub sp} from the irradiated samples was increased as the fluence level increased and was well within the deviation range of the unirradiated data. The TSP had a correlation with the reference temperature (T{sub 0}) from the master curve method using a pre-cracked Charpy V-notched (PCVN) specimen.

  13. Development of a real-time radiological dose assessment system

    Energy Technology Data Exchange (ETDEWEB)

    Han, Moon Hee; Lee, Young Bok; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae; Choi, Young Gil

    1997-07-01

    A radiological dose assessment system named FADAS has been developed. This system is necessary to estimated the radiological consequences against a nuclear accident. Mass-consistent wind field module was adopted for the generation of wind field over the whole domain using the several measured wind data. Random-walk dispersion module is used for the calculation of the distribution of radionuclides in the atmosphere. And volume-equivalent numerical integration method has been developed for the assessment of external gamma exposure given from a randomly distributed radioactive materials and a dose data library has been made for rapid calculation. Field tracer experiments have been carried out for the purpose of analyzing the site-specific meteorological characteristics and increasing the accuracy of wind field generation and atmospheric dispersion module of FADAS. At first, field tracer experiment was carried out over flat terrain covered with rice fields using the gas samplers which were designed and manufactured by the staffs of KAERI. The sampled gas was analyzed using gas chromatograph. SODAR and airsonde were used to measure the upper wind. Korean emergency preparedness system CARE was integrated at Kori 4 nuclear power plants in 1995. One of the main functions of CARE is to estimate the radiological dose. The developed real-time dose assessment system FADAS was adopted in CARE as a tool for the radiological dose assessment. (author). 79 refs., 52 tabs., 94 figs.

  14. Improvement of CUPID code for simulating filmwise steam condensation in the presence of noncondensable gases

    Directory of Open Access Journals (Sweden)

    Jehee Lee

    2015-08-01

    Full Text Available In a nuclear reactor containment, wall condensation forms with noncondensable gases and their accumulation near the condensate film leads to a significant reduction in heat transfer. In the framework of nuclear reactor safety, the film condensation in the presence of noncondensable gases is of high relevance with regards to safety concerns as it is closely associated with peak pressure predictions for containment integrity and the performance of components installed for containment cooling in accident conditions. In the present study, CUPID code, which has been developed by KAERI for the analysis of transient two-phase flows in nuclear reactor components, is improved for simulating film condensation in the presence of noncondensable gases. In order to evaluate the condensate heat transfer accurately in a large system using the two-fluid model, a mass diffusion model, a liquid film model, and a wall film condensation model were implemented into CUPID. For the condensation simulation, a wall function approach with a heat/mass transfer analogy was applied in order to save computational time without considerable refinement for the boundary layer. This paper presents the implemented wall film condensation model, and then introduces the simulation result using the improved CUPID for a conceptual condensation problem in a large system.

  15. Numerical simulations of subcritical reactor kinetics in thermal hydraulic transient phases

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, J.; Park, W. S. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    A subcritical reactor driven by a linear proton accelerator has been considered as a nuclear waste incinerator at Korea Atomic Energy Research Institute (KAERI). Since the multiplication factor of a subcritical reactor is less than unity, to compensate exponentially decreasing fission neutrons, external neutrons form spallation reactions are essentially required for operating the reactor in its steady state. Furthermore, the profile of accelerator beam currents is very important in controlling a subcritical reactor, because the reactor power varies in accordance to the profile of external neutrons. We have developed a code system to find numerical solutions of reactor kinetics equations, which are the simplest dynamic model for controlling reactors. In a due course of our previous numerical study of point kinetics equations for critical reactors, however, we learned that the same code system can be used in studying dynamic behavior of the subcritical reactor. Our major motivation of this paper is to investigate responses of subcritical reactors for small changes in thermal hydraulic parameters. Building a thermal hydraulic model for the subcritical reactor dynamics, we performed numerical simulations for dynamic responses of the reactor based on point kinetics equations with a source term. Linearizing a set of coupled differential equations for reactor responses, we focus our research interest on dynamic responses of the reactor to variations of the thermal hydraulic parameters in transient phases. 5 refs., 8 figs. (Author)

  16. Review of PRA methodology for LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Yang, J.E

    1999-02-01

    Probabilistic Risk Assessment (PRA) has been widely used as a tool to evaluate the safety of NPPs (Nuclear Power Plants), which are in the design stage as well as in operation. Recently, PRA becomes one of the licensing requirements for many existing and new NPPs. KALIMER is a Liquid Metal Fast Breeder Reactor (LMFBR) being developed by KAERI. Since the design concept of KALIMER is similar to that of the PRISM plant developed by GE, it would be appropriate to review the PRA methodology of PRISM as the first step of KALIMER PRA. Hence, in this report summarizes the PRA methodology of PRISM plant, and the required works for the PSA of KALIMER based on the reviewed results. The PRA technology of PRISM plant consists of following five major tasks: (1) development of initiating event list, (2) development of system event tree, (3) development of core response event tree, (4) development of containment response event tree, and (5) consequences and risk estimation. The estimated individual and societal risk measures show that the risk from a PRISM module is substantially less than the NRC goal. Each task is compared to the PRA methodology of Light Water Reactor (LWR)/Pressurized Heavy Water Reactor (PHWR). In the report, each task of PRISM PRA methodology is reviewed and compared to the corresponding part of LWR/PHWR PSA performed in Korea. The parts that are not modeled appropriately in PRISM PRA are identified, and the recommendations for KALIMER PRA are stated. (author). 14 refs., 9 tabs., 4 figs.

  17. Development of Zirconium alloys (for pressure tubes)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Suk; Kwon, Sang Chul; Choo, Ki Nam; Jung, Chung Hwan; Yim, Kyong Soo; Kim, Sung Soo; Baek, Jong Hyuk; Jeong, Yong Hwan; Kim, Kyong Ho; Cho, Hae Dong [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of); Hwang, S. K.; Kim, M. H. [Inha Univ., Incheon (Korea, Republic of); Kwon, S. I [Korea Univ., Seoul (Korea, Republic of); Kim, I. S. [Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of)

    1997-09-01

    The objective of this research is to set up the basic technologies for the evaluation of pressure tube integrity and to develop improved zirconium alloys to prevent pressure tube failures due to DHC and hydride blister caused by excessive creep-down of pressure tubes. The experimental procedure and facilities for characterization of pressure tubes were developed. The basic research related to a better understanding of the in-reactor performances of pressure tubes leads to noticeable findings for the first time : the microstructural effect on corrosion and hydrogen pick-up behavior of Zr-2.5Nb pressure tubes, texture effect on strength and DHC resistance and enhanced recrystallization by Fe in zirconium alloys and etc. Analytical methodology for the assessment of pressure tubes with surface flaws was set up. A joint research is being under way with AECL to determine the fracture toughness of O-8 at the EOL (End of Life) that had been quadruple melted and was taken out of the Wolsung Unit-1 after 10 year operation. In addition, pressure tube with texture controlled is being made along with VNINM in Russia as a joint project between KAERI and Russia. Finally, we succeeded in developing 4 different kinds of zirconium alloys with better corrosion resistance, low hydrogen pickup fraction and higher creep strength. (author). 121 refs., 65 tabs., 260 figs

  18. Development of IASCC Test Facility for Neutron-irradiated Materials

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. W.; Kim, D. J.; Hwang, S. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    From literature review and benchmark studies on recent technologies for IASCC evaluation of highly irradiated stainless steels, the requirements to establish IASCC test facility were drawn. According to the requirements, IASCC test facility for assessment of life time and integrity of RVIs in Korean PWRs will be designed in detail and constructed in hot cells of KAERI. Irradiation assisted stress corrosion cracking (IASCC) has been regarded as the main cause for intergranular cracking incidents in reactor vessel internals (RVIs) in light water reactors (LWRs). IASCC was reported in a fuel rod in the 1960s, a control rod in the 1970s, and a baffle former bolt in recent years. For a proactive management of IASCC of these components, a lot of work has been performed in boiling water reactors (BWRs). From these works, IASCC mechanism and its relation to radiation-induced segregation (RIS), neutron fluence, and applied stress were proposed to describe IASCC behavior of RVIs in BWRs. However, the IASCC mechanism of RVIs in pressurized water reactors (PWRs) is not fully understood yet as compared with that in BWRs owing to a lack of reliable data. Recently, worldwide efforts have been made to investigate the IASCC susceptibility of RVIs in PWRs.

  19. Performance tests for integral reactor nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Dong-Seong; Yim, Jeong-Sik; Lee, Chong-Tak; Kim, Han-Soo; Koo, Yang-Hyun; Lee, Byung-Ho; Cheon, Jin-Sik; Oh, Je-Yong

    2006-02-15

    An integral type reactor SMART plans to utilize metallic Zr-U fuel which is Zr-based alloy with 34{approx}38 wt% U. In order to verify the technologies for the design and manufacturing of the fuel and get a license, performance tests were carried out. Experimental Fuel Assembly (EFA) manufactured in KAERI is being successfully irradiated in the MIR reactor of RIAR from September 4 2004, and it has achieved burnup of 0.21 g/cc as of January 25 2006. Thermal properties of irradiated Zr-U fuel were measured. Up to the phase transformation temperature, thermal diffusivity increased linearly in proportion to temperature. However its dependence on the burnup was not significant. RIA tests with 4 unirradiated Zr-U fuel rods were performed in Kurchatov Institute to establish a safety criterion. In the case of the un-irradiated Zr-U fuel, the energy deposition during the control rod ejection accident should be less than 172 cal/g to prevent the failure accompanying fuel fragmentation and dispersal. Finally the irradiation tests of fuel rods have been performed at HANARO. The HITE-2 test was successfully completed up to a burnup of 0.31 g/cc. The HITE-3 test began in February 2004 and will be continued up to a target burnup of 0.6 g/cc.

  20. Nuclear Fuel Design Technology Development for the Future Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Yang Hyun; Lee, Byung Ho; Cheon, Jin Sik; Oh, Je Yong; Yim, Jeong Sik; Sohn, Dong Seong; Lee, Byung Uk; Ko, Han Suk; So, Dong Sup; Koo, Dae Seo

    2006-04-15

    The test MOX fuels have been irradiated in the Halden reactor, and their burnup attained 40 GWd/t as of October 2005. The fuel temperature and internal pressure were measured by the sensors installed in the fuels and test rig. The COSMOS code, which was developed by KAERI, well predicted in-reactor behavior of MOX fuel. The COSMOS code was verified by OECD-NEA benchmarks, and the result confirmed the superiority of COSMOS code. MOX in-pile database (IFA-629.3, IFA-610.2 and 4) in Halden was also used for the verification of code. The COSMOS code was improved by introducing Graphic User Interface (GUI) and batch mode. The PCMI analysis module was developed and introduced by the new fission gas behavior model. The irradiation test performed under the arbitrary rod internal pressure could also be analyzed with the COSMOS code. Several presentations were made for the preparation to transfer MOX fuel performance analysis code to the industry, and the transfer of COSMOS code to the industry is being discussed. The user manual and COSMOS program (executive file) were provided for the industry to test the performance of COSMOS code. To envisage the direction of research, the MOX fuel research trend of foreign countries, specially focused on USA's GENP policy, was analyzed.