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The Assessment of Exposure Dose of Radiation Workers for Decommissioning Waste in the Radioactive Waste Inspection Building of Low and Intermediate-Level Radioactive Waste Disposal Facility (경주 중·저준위방사성폐기물 처분시설의 방폐물검사건물에서 해체 방사성폐기물 대상 방사선작업종사자의 피폭선량 평가 및 작업조건 도출)

  • Kim, Rin-Ah;Dho, Ho-Seog;Kim, Tae-Man;Cho, Chun-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.2_spc
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    • pp.317-325
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    • 2020
  • The Korea Radioactive Waste Agency plans to expand the storage capacity of radioactive waste by constructing a radioactive waste inspecting building to solve the problem of the lack of inspection space and drum-handling space in the radioactive waste receipt and storage building for the first-stage disposal facility. In this study, the exposure doses of radiation workers that handle new disposal containers for decommissioning waste in the storage areas of the radioactive waste inspecting building were calculated using the Monte Carlo N-particle transport code. The annual collective dose was calculated as a total of 84.8 man-mSv for 304 new disposal containers and an estimated annual 306 working hours for the radiation work. When the 304 new disposal containers (small/medium type) were stored in the storage areas, it was found that 25 radiation workers should be involved in acceptance/disposal inspection, and the estimated exposure dose per worker was calculated as an average annual value of 3.39 mSv. When the radiation workers handle the small containers in high-radiation dose areas, the small containers should be shielded further by increasing the concrete liner thickness to improve the work efficiency and radiation safety of the radiation workers. The results of this study will be useful in establishing the optimal radiation working conditions for radiation workers using the source term and characteristics of decommissioning waste based on actual measurements.

Estimation of R-factor and Seismic Performance for RC IMRFs using N2 Method (N2 Method를 이용한 RC 중간모멘트 연성골조의 반응수정계수 및 내진성능 평가)

  • 윤정배;이철호;최정욱;송진규
    • Journal of the Earthquake Engineering Society of Korea
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    • v.6 no.6
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    • pp.33-39
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    • 2002
  • Response Modification Factor(R-factor) approach is currently implemented to reflect inelastic ductile behavior of the structures and to reduce elastic spectral demands from earthquakes to the design level. However R factors were set empirically and simply based on the professional committee consensus on observed performance of building structures during past earthquakes. Consequently some major shortcomings linked to the current R factor approach have been pointed out. Using reinforced concrete intermediate moment-resisting frames(RC IMRFs), an analytical procedure is presented in this paper to establish R factor rationally. To this end, analytical R values were evaluated based on N2 Method and compared with the values recommended by IBC 2000. Overall, the analytical results correlated well with the code values. However the results also revealed that R factor might strongly depend on the system fundamental period. As evidenced by the interstory drift index(IDI) analysis results of this study, current R-factor based(or, Life Safety based) design tends to fail in fulfilling other implicit and hopeful performance objectives such as immediate Occupancy and Collapse Prevention. Performance based design(PBD) appears to be a promising approach to meet the multi level seismic performance objectives assigned to the building structures of nowadays.

An Experimental Study on the Clogging of Sand Filter in a Model Filtration-Pond (천변여과지 모형에서 여재모래의 폐색현상 실험연구)

  • Jeong, Jae-Min;Kim, Seung-Hyun
    • Journal of Korean Society of Environmental Engineers
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    • v.35 no.9
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    • pp.681-685
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    • 2013
  • A pilot-scale sand-box experiment was performed in order to investigate the effect of cross-flow velocity on the clogging of the filter sand in a model filtration pond. The clogging phenomenon was observed during the operation with the cross-flow varied in stages in a range of 0~40 cm/sec, and the experimental result was analyzed using a numerical code. Results showed that the cross-flow velocity in this range had no influence on the development of clogging and that clogging occurred mostly on the filter-surface. It was found that while the production rate decreased from $5m^3/m^2-day$ to $3m^3/m^2-day$ the clogging coefficient of the top 50 cm layer increased up to about 30,000 sec, which corresponded to 87% of the clogging coefficient of the total 2.4 m layer. Of the clogging coefficient of the top 50 cm layer, surface clogging constituted 90% while the other 10% was intermediate clogging. It was also found that the surface clogging increased while the intermediate clogging remained constant as the operation continued, and that filtrate turbidity along the filtration depth remained constant in spite of the increase in clogging.

Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND)

  • Kim, Ho Sik;NO, Hee Cheon;Jo, YuGwon;Wibisono, Andhika Feri;Park, Byung Ha;Choi, Jinyoung;Lee, Jeong Ik;Jeong, Yong Hoon;Cho, Nam Zin
    • Nuclear Engineering and Technology
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    • v.47 no.3
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    • pp.293-305
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    • 2015
  • In this paper, we suggest the conceptual design of a water-cooled reactor system for a low-pressure inherent heat sink nuclear desalination plant (LIND) that applies the safety-related design concepts of high temperature gas-cooled reactors to a water-cooled reactor for inherent and passive safety features. Through a scoping analysis, we found that the current LIND design satisfied several essential thermal-hydraulic and neutronic design requirements. In a thermal-hydraulic analysis using an analytical method based on the Wooton-Epstein correlation, we checked the possibility of safely removing decay heat through the steel containment even if all the active safety systems failed. In a neutronic analysis using the Monte Carlo N-particle transport code, we estimated a cycle length of approximately 6 years under 200 $MW_{th}$ and 4.5% enrichment. The very long cycle length and simple safety features minimize the burdens from the operation, maintenance, and spent-fuel management, with a positive impact on the economic feasibility. Finally, because a nuclear reactor should not be directly coupled to a desalination system to prevent the leakage of radioactive material into the desalinated water, three types of intermediate systems were studied: a steam producing system, a hot water system, and an organic Rankine cycle system.

Comparison and Performance analysis of Wavelet OFDM system and FD-OFDM (웨이블릿 OFDM 시스템과 FD-OFDM 시스템 성능 비교 분석)

  • Lee, Junseo;Kim, Ji-Hoon;Kim, Whanwoo
    • Journal of the Institute of Electronics and Information Engineers
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    • v.50 no.7
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    • pp.34-42
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    • 2013
  • In this paper, we compare the performance of wavelet OFDM (Orthogonal Frequency Division Multiplexing) and FD-OFDM(Frequency diversity OFDM) system with conventional OFDM system. Wavelet OFDM system uses wavelet transform rather than Fourier transform and contains intermediate characteristics of CDM (Code Division Multiplexing) and OFDM. In wavelet OFDM system, inter-symbol interference (ISI) can be suppressed effectively and adjacent channel interference can be also minimized well. In FD-OFDM system, each parallel branch symbol is multiplied by the orthogonal sequence and distributed into all sub-carriers. Then, each sub-carrier transmits information composed of the symbol components of all parallel branches in the given frame. FD-OFDM contains the frequency diversity characteristic and, therefore, FD-OFDM can be robust to the narrowband interference. For the comparison among different systems, BER (Bit-Error Rate) performances are evaluated in the presence of narrow-band interference and a harmonic noise channel. From the evaluation results, compared to the conventional OFDM, wavelet OFDM and FD-OFDM shows better robustness against the interference and, especially, wavelet OFDM is the most robust in harmonic noise channel.

An Evaluation on the Radiation Shielding of the Radwaste Drum Assay Facility (방사성폐기물드럼 핵종재고량 평가시설 구축에 따른 방사선차폐 영향평가)

  • Ji, Young-Yong;Kwak, Kyung-Kil;Hong, Dae-Seok;Shon, Jong-Sik
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.10 no.2
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    • pp.117-123
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    • 2012
  • In order to dispose of the LILW(low and intermediate level radioactive waste) stored at KAERI, the radwaste drum assay system will be introduced to evaluate the radioisotopes inventory of stored drums. At present, the construction project of the dedicated assay facility to operate it and carry out routine maintenance of that equipment has been conducting at the radwaste treatment facility. Since that facility will be constructed in front of a 1st radwaste storage facility as well as the radwaste drums to be assayed and the transmission source in the radwaste drum assay system are in that facility, they could act as the radioactive sources and then, would affect the dose rate at the inside and the outside of the facility. Therefore, the radiation shielding should be evaluated through the concrete wall near to the radioactive sources whether the wall thickness is sufficient against the regulations. In this study, the radiation safety for the concrete wall around the radiation controlled area in the radwaste drum assay facility was evaluated by the MCNP code. From the evaluation results, the thickness of those concrete walls which are under consideration of about 30 cm was enough to shield the radiation from the radioactive sources.

The Effect of Cross-Cumulation of Rule of Origin: Case Study of Korea-Canada FTA in terms of Auto Parts Import from U.S. (원산지 교차누적 효과 분석: 한-캐나다 FTA를 활용한 대(對)미 자동차 부품 수입을 중심으로)

  • Kim, Kyu-Rim;Ra, Hee-Ryang
    • Korea Trade Review
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    • v.43 no.1
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    • pp.109-130
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    • 2018
  • The cumulative standard is one of the criteria determining the origin of imported goods and is a provision that allows non-origin materials to be treated as origin goods when satisfying certain conditions. Regarding the Korea-Canada FTA, new cumulative standards were applied concerning cross accumulation of automobile products. It would benefit U.S. originating intermediate goods of HS code chapter 84, 85, 87, and 94 obtained into HS code heading from 8701 into 8706. We examine the effectiveness of crossover cumulative standards through the change in the import values of 84, 85, 87, 94, which are target items for cross cumulation. Only items designated for automobile parts were selected and analyzed. From the estimation results, significant changes appeared in 20 of the 35 items. It was found that the import amount increased significantly as of January 2015 or the rate of change in trend increases more than before. In addition, the estimation results show that Korean auto companies utilizing the cumulative standards through increased imports of auto parts form the U.S.

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LARGE EDDY SIMULATION OF THERMAL STRIPING IN THE UPPER PLENUM OF FAST REACTOR (대와동모사법을 사용한 고속로 상부플레넘에서의 thermal sriping 해석)

  • Choi, S.K.;Han, J.W.;Kim, D.;Lee, T.H.
    • Journal of computational fluids engineering
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    • v.19 no.4
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    • pp.29-36
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    • 2014
  • A computational study of a thermal striping in the upper plenum of PGSFR(Prototype Generation-IV Sodium-cooled Fast Reactor) being developed at the KAERI(Korea Atomic Energy Research Institute) is presented. The LES(Large Eddy Simulation) approach is employed for the simulation of thermal striping in the upper plenum of the PGSFR. The LES is performed using the WALE (Wall-Adapting Local Eddy-viscosity) model. More than 19.7 million unstructured elements are generated in upper plenum region of the PGSFR using the CFX-Mesh commercial code. The time-averaged velocity components and temperature field in the complicated upper plenum of the PGSFR are presented. The time history of temperature fluctuation at the eight locations of solid walls of UIS(Upper Internal Structure) and IHX(Intermediate Heat eXchanger) are additionally stored. It has been confirmed that the most vulnerable regions to thermal striping are the first plate of UIS. From the temporal variation of temperature at the solid walls, it was possible to find the locations where the thermal stress is large and need to assess whether the solid structures can endure the thermal stress during the reactor life time.

Collapse response assessment of low-rise buildings with irregularities in plan

  • Manie, Salar;Moghadam, Abdoreza S.;Ghafory-Ashtiany, Mohsen
    • Earthquakes and Structures
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    • v.9 no.1
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    • pp.49-71
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    • 2015
  • The present paper aims at evaluating damage and collapse behavior of low-rise buildings with unidirectional mass irregularities in plan (torsional buildings). In previous earthquake events, such buildings have been exposed to extensive damages and even total collapse in some cases. To investigate the performance and collapse behavior of such buildings from probabilistic points of view, three-dimensional three and six-story reinforced concrete models with unidirectional mass eccentricities ranging from 0% to 30% and designed with modern seismic design code provisions specific to intermediate ductility class were subjected to nonlinear static as well as extensive nonlinear incremental dynamic analysis (IDA) under a set of far-field real ground motions containing 21 two-component records. Performance of each model was then examined by means of calculating conventional seismic design parameters including the response reduction (R), structural overstrength (${\Omega}$) and structural ductility (${\mu}$) factors, calculation of probability distribution of maximum inter-story drift responses in two orthogonal directions and calculation collapse margin ratio (CMR) as an indicator of performance. Results demonstrate that substantial differences exist between the behavior of regular and irregular buildings in terms of lateral load capacity and collapse margin ratio. Also, results indicate that current seismic design parameters could be non-conservative for buildings with high levels of plan eccentricity and such structures do not meet the target "life safety" performance level based on safety margin against collapse. The adverse effects of plan irregularity on collapse safety of structures are more pronounced as the number of stories increases.

Phenomenological Modeling of Newly Discovered Eclipsing Binary 2MASS J18024395 + 4003309 = VSX J180243.9+400331

  • Andronov, Ivan L.;Kim, Yonggi;Kim, Young-Hee;Yoon, Joh-Na;Chinarova, Lidia L.;Tkachenko, Mariia G.
    • Journal of Astronomy and Space Sciences
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    • v.32 no.2
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    • pp.127-136
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    • 2015
  • We present a by-product of our long term photometric monitoring of cataclysmic variables. 2MASS J18024395 +4003309 = VSX J180243.9 +400331 was discovered in the field of the intermediate polar V1323 Her observed using the Korean 1-m telescope located at Mt. Lemmon, USA. An analysis of the two-color VR CCD observations of this variable covers all the phase intervals for the first time. The light curves show this object can be classified as an Algol-type variable with tidally distorted components, and an asymmetry of the maxima (the O'Connell effect). The periodogram analysis confirms the cycle numbering of Andronov et al. (2012) and for the initial approximation, the ephemeris is used as follows: Min I. BJD = 2456074.4904+0.3348837E. For phenomenological modeling, we used the trigonometric polynomial approximation of statistically optimal degree, and a recent method "NAV" ("New Algol Variable") using local specific shapes for the eclipse. Methodological aspects and estimates of the physical parameters based on analysis of phenomenological parameters are presented. As results of our phenomenological model, we obtained for the inclination $i=90^{\circ}$, $M_1=0.745M_{\odot}$, $M_2=0.854M_{\odot}$, $M=M_1+M_2=1.599M_{\odot}$, the orbital separation $a=1.65{\cdot}10^9m=2.37R_{\odot}$ and relative radii $r_1=R_1/a=0.314$ and $r_2=R_2/a=0.360$. These estimates may be used as preliminary starting values for further modeling using extended physical models based on the Wilson & Devinney (1971) code and it's extensions