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New Magnetic Anomaly Map of the Antarctic
Golynsky, A. V.,Ferraccioli, F.,Hong, J. K.,Golynsky, D. A.,von Frese, R. R. B.,Young, D. A.,Blankenship, D. D.,Holt, J. W.,Ivanov, S. V.,Kiselev, A. V.,Masolov, V. N.,Eagles, G.,Gohl, K.,Jokat, W.,Da American Geophysical Union 2018 Geophysical research letters Vol.45 No.13
Bratton, Ryan N.,Avramova, M.,Ivanov, K. Korean Nuclear Society 2014 Nuclear Engineering and Technology Vol.46 No.3
A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).
Current practices and recent advances in condition assessment of aged ships
Rizzo, C. M.,Paik, J. K.,Brennan, F.,Carlsen, C. A.,Daley, C.,Garbatov, Y.,Ivanov, L.,Simonsen, B. C.,Yamamoto, N.,Zhuang, H. Z. Taylor Francis 2007 SHIPS AND OFFSHORE STRUCTURES Vol.2 No.3
<P> Ship structures are likely to be subject to age-related deterioration such as corrosion wastage, cracking or mechanical damage. It has reportedly been recognised that such age-related deterioration is almost always involved in the catastrophic failures of ship structures including total losses. While such accidents typically cause concern to the public, maintenance and repair of aged structures is quite costly and complex. It is thus of great importance to develop advanced technologies allowing for proper management and control of such age-related deterioration. This paper summarises the report of the ISSC 2006 Committee V.6 presenting current practices, recent advances and future trends on condition assessment of aged ships. This includes assessment of the structural condition in view of the serviceability and safety, methods for repair, quantification of strength of deteriorated and repaired ships (as well as criteria for acceptable damage), with due account of the uncertainties involved. Consideration is also given to cost-benefit and risk-based decision procedures for remedial actions.</P>
RYAN N. BRATTON,M.AVRAMOVA,K. IVANOV 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.3
A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark forUncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of availableuncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safetycalculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phaseseach of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known asthe “Neutronics Phase”, which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughoutsteady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured dataare available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, andVVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments andthe SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutronnuclidereactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters ofneutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuityfactors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done toreduce uncertainties in key nuclide reaction uncertainties (i.e.: 238U radiative capture and inelastic scattering (n, n’) as well asthe average number of neutrons released per fission event of 239Pu).
Fabrication of an Yttria Thin-Wall Tube by Radial Magnetic Pulsed Compaction of Powder-Based Tapes
Lee, Jung G.,Hong, S. J.,Park, J. J.,Lee, M. K.,Ivanov, V. V.,Rhee, C. K. The Japan Institute of Metals 2010 MATERIALS TRANSACTIONS Vol.51 No.9
<P>Highly dense and homogeneous yttria (Y<SUB>2</SUB>O<SUB>3</SUB>) thin-wall tubes have been successfully fabricated by applying tape-casting and radial magnetic pulsed compaction (RMPC) followed by thermal sintering. Since a homogeneous density distribution was obtained in the RMPCed compact, by using the Y<SUB>2</SUB>O<SUB>3</SUB>-based tape instead of a stuck of raw powder, cracking and bending were inhibited throughout the process up to the final sintered body. The relative density of the resultant tube reached 99.9%, and the structure was very fine with grain sizes of 2∼5 μm. Moreover, when the granulated powder was used as the precursor of the tape, the thermal densification was promoted due to its enhanced sinterability as compared to the raw powder.</P>
Structural Design of the KSTAR Central Solenoid Structure
사정우,A. Arneman,A. Alekseev,C. H. Choi,D. P. Ivanov,H. K. Park,H. T. Kim,박주식,K. H. Hong 한국물리학회 2006 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.49 No.III
The KSTAR central solenoid (CS) coils consist of 4 pairs of superconducting coils, which have updown symmetry and a set of structure with electrical insulation. The structure gives pre-compression in a vertical direction on the coil stack to sustain the contact between coils. The CS structure has the important design requirement that it should protect the CS coils from electromagnetic and thermal loads. The space inside the CS coil has complicated components such as long coil leads and cooling lines and there are many limits in designing the supports. Thus, in order to solve the interference problem between other structural components, a design for the CS structure has been proposed. Also structural analysis has been performed to verify the structural integrity.
Kanaya, Y.,Irie, H.,Takashima, H.,Iwabuchi, H.,Akimoto, H.,Sudo, K.,Gu, M.,Chong, J.,Kim, Y. J.,Lee, H.,Li, A.,Si, F.,Xu, J.,Xie, P.-H.,Liu, W.-Q.,Dzhola, A.,Postylyakov, O.,Ivanov, V.,Grechko, E.,Ter Copernicus GmbH 2014 Atmospheric Chemistry and Physics Vol.14 No.15
<P>Abstract. We conducted long-term network observations using standardized Multi-Axis Differential optical absorption spectroscopy (MAX-DOAS) instruments in Russia and ASia (MADRAS) from 2007 onwards and made the first synthetic data analysis. At seven locations (Cape Hedo, Fukue and Yokosuka in Japan, Hefei in China, Gwangju in Korea, and Tomsk and Zvenigorod in Russia) with different levels of pollution, we obtained 80 927 retrievals of tropospheric NO2 vertical column density (TropoNO2VCD) and aerosol optical depth (AOD). In the technique, the optimal estimation of the TropoNO2VCD and its profile was performed using aerosol information derived from O4 absorbances simultaneously observed at 460-490 nm. This large data set was used to analyze NO2 climatology systematically, including temporal variations from the seasonal to the diurnal scale. The results were compared with Ozone Monitoring Instrument (OMI) satellite observations and global model simulations. Two NO2 retrievals of OMI satellite data (NASA ver. 2.1 and Dutch OMI NO2 (DOMINO) ver. 2.0) generally showed close correlations with those derived from MAX-DOAS observations, but had low biases of up to ~50%. The bias was distinct when NO2 was abundantly present near the surface and when the AOD was high, suggesting a possibility of incomplete accounting of NO2 near the surface under relatively high aerosol conditions for the satellite observations. Except for constant biases, the satellite observations showed nearly perfect seasonal agreement with MAX-DOAS observations, suggesting that the analysis of seasonal features of the satellite data were robust. Weekend reduction in the TropoNO2VCD found at Yokosuka and Gwangju was absent at Hefei, implying that the major sources had different weekly variation patterns. While the TropoNO2VCD generally decreased during the midday hours, it increased exceptionally at urban/suburban locations (Yokosuka, Gwangju, and Hefei) during winter. A global chemical transport model, MIROC-ESM-CHEM (Model for Interdisciplinary Research on Climate-Earth System Model-Chemistry), was validated for the first time with respect to background NO2 column densities during summer at Cape Hedo and Fukue in the clean marine atmosphere. </P>