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Kim, I.; Sohn, G.H.
Development of fracture mechanics techniques for evaluation of structual integrity of primary pressure boundary components: pt. 1-41982
Development of fracture mechanics techniques for evaluation of structual integrity of primary pressure boundary components: pt. 1-41982
AbstractAbstract
[en] Extensive revising and supplemental work changed the original FAPCO of 1980 with 5 subprograms to one consisting of 18 subprograms. FAPCO was evaluated by checking the accuracy of parameters and sample problem analysis. User's manual was also written. (Author)
Primary Subject
Source
Korea Advanced Energy Research Inst., Seoul (Republic of Korea); 416 p; 1982; pt. 1, p. 9-87
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AbstractAbstract
No abstract available
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Journal Article
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Physical Review. D, Particles Fields; v. 6(4); p. 1185-1188
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AbstractAbstract
[en] The magnetic jack type Control Element Drive Mechanism (CEDM) for Korean Standard Nuclear Power Plant (KSNP) is an electromechanical device which provides controlled linear motion to the Control Element Assembly (CEA) through the Extension Shaft Assembly (ESA) in response to operational signals received from the Control Element Drive Mechanism Control System (CEDMCS). The CEDM is operated by applying localized magnetic flux fields to movable latch and lift magnets, which are in the coolant pressure boundary. The CEDM design had been developed through electromechanical testing of the system including the magnetic force lifting the ESA. But it will be inefficient if parametric studies should be performed to improve the CEDM by test due to the consumption of high cost and long duration. So it becomes necessary to develop a computational model to simulate the electromagnetic characteristics of the CEDM to improve the CEDM design efficiently. In this paper, the electromagnetic analysis using a 2D finite element model has been carried out to simulate magnetic force of the lift magnet of the CEDM, to provide effective evaluation between leakage flux and lift force and to compare with test results. Analysis results show the lift force satisfied the test results and design requirement and the lift force depend on the shape of the components, leakage flux and B-H curve
Primary Subject
Source
Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2002; [12 p.]; 2002 autumn meeting of the KNS; Yongpyoung (Korea, Republic of); 24-25 Oct 2002; Available from KNS, Taejon (KR); 9 refs, 7 figs, 1 tab
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Miscellaneous
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Conference
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AbstractAbstract
[en] The KZU-482 combined memory of increased capacity intended for systems including the KKI-661 type crate-controller or other control blocks utilizing the dataway of Intel 8080 microprocessor is described. The module comprises reprogrammed memory of 8 kbyte and mass memory of 48 kbyte. Communication of the module with control blocks (crate controller, channel of direct access to memory) is realized by means of the CAMAC dataway. The considered module is utilized in an on-line control system of cryogenic helium facility and in a control device of the EC-1055M computer terminal
Original Title
Kombinirovannoe zapominayushchee ustrojstvo tipa KZU-482
Secondary Subject
Source
Joint Inst. for Nuclear Research, Dubna (USSR); p. 206-208; 1985; p. 206-208; 12. International symposium on nuclear electronics; Dubna (USSR); 2-6 Jul 1985
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Report
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Conference
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Kim, H. J.; Kim, I. K.; Shin, A. D.
Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)2004
Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)2004
AbstractAbstract
[en] Multidimensional thermal-hydraulic code calculations are necessary to predict complex thermal-hydraulic phenomena within the downcomer during LBLOCA calculation. The main objective of present study is to evaluate the TRACE code capability with DVI related Upper Plenum Test Facility Data, which is on the developing by US-NRC. Another objective is to develop the APR-1400 plant standard input deck preparing the LBLOCA calculation using TRACE code. TRACE input decks for UPTF Test 6,7,21 was developed and TRACE code was evaluated with theses input decks. The result of comparison on lower plenum penetration rate with data showed that TRACE code predict reasonable lower plenum penetration rate. On the calculation of Test 21(Run 272) and Test 5(Run 062), high subcooled water is injected, TRACE code overprediced the bypass rate. Analysis showed that the condensation model in TRACE code overpredict the condensation of steam within upper downcomer region. It is identified that the condensation model in TRACE code needs improvement. TRACE code input deck for APR-1400 was developed and preliminary LBLOCA case was calculated. The result was very sensitive to its input deck change in terms of peak cladding temperature. it showed that the quality assurance during input deck development is crucial especially in the best estimate thermal-hydraulic calculation
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Dec 2004; 85 p; Also available from KINS; 18 refs, 14 figs, 11 tabs
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Kim, T. K.; Jin, C. E.; Kim, I. Y.
Korea Power Engineering Co., Inc., Seoul (Korea, Republic of)1999
Korea Power Engineering Co., Inc., Seoul (Korea, Republic of)1999
AbstractAbstract
[en] This paper introduces the basic features of the various types of Reactor Vessel (RV) head area structures used in the nuclear power plant and developed in these days. The previous RV head area structures consist of many components that needed to be disassembled, removed and stored individually during every refueling outage. The Integrated Head Assembly (IHA) developed by KOPEC is considered as a mechanical system that combines the RV head lifting device, the CEDM seismic support device, the missile shield, the CEDM cooling components and the head area cable system into one efficient assembly, which can be handled together as a single assembly. Also, the IHA is designed to accommodate a Multiple Stud Tensioner (MST). It is expected that IHA will contribute to reduction in refueling outage time as well as reduction in radiation exposure to operators. (author)
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9 refs., 1 tab., 15 figs.
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Journal Article
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Power Engineering; ISSN 1225-8016; ; v. 10(2); p. 117-126
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AbstractAbstract
[en] A single equal channel angular pressing at various temperatures (473 to ∼873 K) was conducted on commercially pure titanium in order to investigate the effects of the pressing temperature on the microstructures. Optical and scanning electron microscopy showed that fine shear traces, elongated along the direction of approximately 25 deg. inclined to the longitudinal axis of a sample, were well developed over the whole temperature range. Transmission electron microscopy revealed that the shear traces were composed of parallel bands having a width of a submicrometer scale. It was also revealed that the bands of a sample pressed at 473 K resulted from slip but those of samples pressed above 523 K resulted from {101-bar1} deformation twinning. For the twinned samples, the twin density initially increased with temperature up to 623 K and then decreased at higher temperatures. Contrary to the changes of the twin density, the dislocation density decreased with temperature up to 623 K and then increased. At a pressing temperature of 873 K, fine recrystallized grains were also observed to appear in the vicinity of the shear traces. These anomalous microstructural changes with the pressing temperature were discussed in terms of the characteristics of {101-bar1} twinning produced by equal channel angular pressing
Primary Subject
Source
S0921509302003180; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
Journal
Materials Science and Engineering. A, Structural Materials: Properties, Microstructure and Processing; ISSN 0921-5093; ; CODEN MSAPE3; v. 342(1-2); p. 302-310
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AbstractAbstract
[en] The development of microstructure during equal-channel angular pressing (ECAP) of commercial-purity titanium was investigated to establish the mechanisms of grain refinement and strain accommodation. Samples were deformed at 623 K via three different processing routes: A, B, and C. After the first pass, transmission electron microscopy (TEM) revealed that the strain imposed by pressing was accommodated mainly by {101-bar1} deformation twinning. During the second pass, the deformation mechanism changed to dislocation slip on a system which depended on the specific route. For route C, prism (a) and pyramidal (c+a) slip occurred within alternating twin bands. For route B, prism a slip was the main deformation mechanism. For route A, deformation was controlled by basal a slip and micro-twinning in alternating twin bands. The variation in deformation behavior was interpreted in terms of the texture formed during the first pass and the Schmid factors for slip during subsequent deformation
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S1359645402005013; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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AbstractAbstract
[en] The structure of {1 0 1 1} deformation twins in commercially pure titanium processed by equal channel angular pressing was examined by high resolution electron microscopy in an attempt to explain the accommodation of shear strain imposed by the pressing. The results indicate that various twinning dislocations were activated to produce twins that accommodated the imposed shear strain
Primary Subject
Source
S1359646202005134; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Kim, I. T.; Lee, H. S.; Hur, J. M.; Kim, J. G.; Ahn, D. H.; Cho, Y. Z.; Kang, H. S.; Kwon, S. W.; Kim, G. H.; Kim, I. S.
Korea Atomic Energy Research Institute, Daejon (Korea, Republic of)2012
Korea Atomic Energy Research Institute, Daejon (Korea, Republic of)2012
AbstractAbstract
[en] This study aims to manufacture an integrated pyroprocessing units for PRIDE facility based on the technologies developed under the national long term R and D program. - The integrated units for PRIDE facility as remote control-enabled equipment were successfully established through 3D simulation tests using the unit designs and remote control tests using mock-up equipment of the units. - The establishment of integrated pyroprocessing units for Pride facility, critical gap R and D program was accomplished as a part of 'Joint Nuclear Fuel Cycle(JNFC)' study between Korea and USA
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Apr 2012; 253 p; 31 refs, 184 figs, 21 tabs
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