• Title/Summary/Keyword: Kori

Search Result 414, Processing Time 0.027 seconds

Multi-group Diffusion Analysis on Kori Reactor's Fuel Loading Patterns (고리원자로 핵연료의 장진방법에 대한 다군확산적 효과분석)

  • Chang Kun Lee
    • 전기의세계
    • /
    • v.22 no.1
    • /
    • pp.20-27
    • /
    • 1973
  • The multi-group diffusion theory is applied to the analysis of the currently constructing Kori reactor core which is to be refuelled by 3-region fuel loading pattern and also to the comparative study on a conceptually designed 5-region reactor core, under the condition that, apart from the thermal-hydraulic considerations, all the input data referred to here in are assumed to be identical for both cases. The numerical calculation is carried out for quantitative analysis of the characteristics of the two fuel loading patterns in details, and the calculated results show that, so far as the nuclear aspects are concerned, the characteristics of the 5-region reactor core are proved to be superior to those of Kori's 3-region reactor core in general.

  • PDF

Non-Integrated Standalone Test of An Nuclear Steam Supply System Thermal-Hydraulic Program for the Westinghouse Type Nuclear Power Plant Simulator Using A Best-Estimate Code (최적 계통분석 코드를 이용한 웨스팅하우스형 원자력발전소 시뮬레이터용 핵 증기 공급 계통 열수력 프로그램 독자평가 및 시험)

  • 서인용;이명수;이용관;서재승;권순일
    • Proceedings of the Korea Society for Simulation Conference
    • /
    • 2004.05a
    • /
    • pp.101-108
    • /
    • 2004
  • KEPRI has developed an Nuclear Steam Supply System(NSSS) thermal-hydraulics simulation program (called ARTS-KORI), based on the best-estimate system code, RETRAN, as a part of the development project for the KORI unit 1 Nuclear Power Plant Simulator. A number of code modifications, such as simplifications and removing of discontinuities of the physical correlations, were made in order to change the RETRAN code as an nuclear Steam Supply System thermal-hydraulics engine in the simulator. Some simplified models and a backup system were also developed. This paper briefly presents the results of non-integrated standalone test of ARTS-KORI.

  • PDF

Calculation of Reactor Pressure Vessel Fluence Using TORT Code

  • Shin, Chul-Ho;Kim, Jong kyung
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1998.05b
    • /
    • pp.771-776
    • /
    • 1998
  • TORT is employed for fast neutron fluence calculation at the reactor pressure vessel. KORI Unit 1 reactor at cycle 1 is modeled for this calculation. Three-dimensional cycle averaged assembly power distributions for KORI Vnit 1 at cycle 1 are calculated by using the core physics code, NESTLE 5.0. The root mean square error is within 4.3% compared with NDR (Nuclear Design Report) far all burnup steps. The C/E (Calculated/Experimental) values for the in-vessel dosimeters distribute between 0.98 and 1.36. The most updated cross-section library. BUGLE-96 based on ENDF/B-VI is used for the neutron fluence calculation. The makimum fast neutron nun calculated on reactor pressure vessel for KORI Unit 1 operated for 411.41 effgctive full power days is 1.784x10$^{18}$ n/$\textrm{cm}^2$. The position of the maximum neutron fluence in RPV wall 1/4 T is nearby 60cm below the midplane at zero degree.

  • PDF

Feeding Habits of Juvenile Lophius litulon in the Coastal Waters of Kori, Korea (고리 주변 해역에서 채집된 황아귀 (Lophius litulon) 유어의 식성)

  • BAECK Gun Wook;HUH Sung-Hoi
    • Korean Journal of Fisheries and Aquatic Sciences
    • /
    • v.36 no.6
    • /
    • pp.695-699
    • /
    • 2003
  • We examined the stomach contents of juvenile Lophius litulon, which were collected monthly in the coastal waters of Kori, Korea from January to December, 1996. L. litulon was a bottom feeding carnivore which mainly consumed fish, euphausiids, sagittoids, and shrimp. Its diet also included small quantities of copepods amphipods, and stomatopods. It showed distinct ontogenetic changes in feeding habits. Small individuals (1-2 cm SL) mainly preyed on sagittoids and euphausiids. However, individuals eve, 3 cm SL mainly preyed on fish and shrimp.

A Study on the Marin Algae at the Coast of Kori Nuclear Power Plant 1. Variation of Algal Community during 1977~1978 (고리원자력발전소 주변 해조류에 관한 연구 1. 1977~1978년의 해조군업의 변화)

  • 김영환
    • Journal of Plant Biology
    • /
    • v.23 no.1
    • /
    • pp.3-10
    • /
    • 1980
  • Effects of thermal effluents on the marine algal communities were investigated with the quadrat method during June, 1977-December, 1978, at the intertidal zone of Kori Nuclear Power Plant, Southeast Coast of Korea. As a result, both the number of algal species occurred in quadrat (50$\times$50cm) and the total coverage were observed to be decreased in June, 1978, at three sites near the discharge point compared with those of previous year but being recovered afterwards. The representative dominant species at the coast of Kori Nuclear Power Plant were, on the whole, Corallina pilulifera, Pachymeniopsis elliptica, and Chondrus ocellatus. Among the species, the coverage of Corallina pilulifera appeared to be rather increased, while the vegetation of Chondria crassicaulis was found to be decreased particularly in 1978. Total 102 species (3 blue-green, 16 green, 30 brown, and 53 red algae) of marine algae were identified in this study. Among them 71 species were common to 133 species reported by previous investigators during 1969-1970.

  • PDF

Derivation of preliminary derived concentration guideline levels for surface soil at Kori Unit 1 by RESRAD probabilistic analysis

  • Byon, Jihyang;Park, Sangjune;Ahn, Seokyoung
    • Nuclear Engineering and Technology
    • /
    • v.50 no.8
    • /
    • pp.1289-1297
    • /
    • 2018
  • Preliminary surface soil Derived Concentration Guideline Levels (DCGLs) were derived conforming to the Multi-Agency Radiation Site Survey and Investigation Manual (MARSSIM) procedure for the site release and reuse of Kori Unit 1 in Korea. Based on the decommissioning experiences of the U.S. nuclear power plants, a suite of residual radionuclides was determined, and uncertainties contributed to the resultant dose by the input parameters were quantified via the sensitivity analysis of parameters. The peak of the mean dose was obtained via the probabilistic analysis of the RESRAD (RESidual RADioactivity)-ONSITE code. Consequently, $DCGL_w$ of Kori Unit 1 in accordance with two scenarios, industrial worker and residential farmer scenario, were derived and the results were compared respectively with other NPPs. It could be used as a basic guideline for establishing regulatory standards for reuse planning, designing the site characterization surveys and implementing final status survey (FSS).

Estimation of Effective Dose to Residents Due to Hypothetical Accidents During Dismantling of Steam Generator

  • Kyeong-Ju Lee;Chang-Lak Kim
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.21 no.2
    • /
    • pp.183-191
    • /
    • 2023
  • The potential impact of hypothetical accidents that occur during the immediate and deferred dismantling of the Kori Unit 1 steam generator has been comprehensively evaluated. The evaluation includes determining the inventory of radionuclides in the Steam Generator based on surface contamination measurements, assuming a rate of release for each accident scenario, and applying external and internal exposure dose coefficients to assess the effects of radionuclides on human health. The evaluation also includes calculating the atmospheric dispersion factor using the PAVAN code and analyzing three years of meteorological data from Kori NPP to determine the degree of diffusion of radionuclides in the atmosphere. Overall, the effective dose for residents living in the Exclusion Area Boundary (EAB) of Kori NPP is predicted, an it is found that the maximum level of the dose is 0.034% compared to the annual dose limit of 1 mSv for the general public. This implies that the potential impact of hypothetical accidents on human health discussed above is within acceptable limits.

Analyses of SGTR Accident With Mihama Unit Experience (미하마 원전경험에 대한 SGTR 사고해석)

  • Lee, S.H.;Kim, K.;Kim, H.J.;Eun, Y.S.
    • Nuclear Engineering and Technology
    • /
    • v.26 no.1
    • /
    • pp.41-53
    • /
    • 1994
  • A SGTR accident postulated at Kori unit 1 is simulated with Mihama unit experience, which occurred on February 1991, to evaluate the capability of plant to cope with the transient. The system design and plant conditions of Kori Unit 1 are much similar with those of Mihama Unit 2. Therefore, special concern has been given to evaluate the sequence and the resulting consequence of the postulated SGTR accident at the Kori unit 1 An analysis is peformed as realistically as possible, with following the EOP of Kori unit 1. The result indicates that the leak through tube break terminates within about forty minutes, and the Kori unit 1 may be sufficient to cope with SGTR accident with same type of sequence. However, the reconsideration may be required for the design of Kori unit 1 which disconnects non-safety AC power from off-site power on SI signal generation. It may be pointed out that the content of EOP for SGTR accident is not enough to require operator's proper judgements. An analysis of SGTR accident tested in the LSTF which simulated the SGTR accident at the Mihama Unit 2 is peformed using the RELAP5/MOD3. The results indicates that the code yields in general good agreement with the test, except the break flowrate at the early stage of the event.

  • PDF

Dispersion Pattern of CoolingWater of Kori Atomic Power Station Using Thermal Infrared Data (열적외선 자료에 의한 고리 원자력발전소의 냉각수 확산에 대한 연구)

  • 姜必鍾;智光薰
    • Korean Journal of Remote Sensing
    • /
    • v.3 no.2
    • /
    • pp.81-87
    • /
    • 1987
  • The study was to analysis the dispersion of the cooling water of Kori atomic power station using thermal infrared data. The dispersion pattern of the cooling water analysis clearly on the LANDSAT TM band 6. It was changed due to tidal current, that is, the cooling water disperses north-eastern direction during the low tide and southweatern direction during the high tide. The relative temperature distribution was mapped through the density slicing method on the images.

Temporal and Spatial Variations of Phytoplankton Communities in the Pelagic Environment of Kori, Korea (고리해역 표영환경내 식물플랑크톤 군집의 시공간적 변화)

  • 여환구;허성회
    • Korean Journal of Environmental Biology
    • /
    • v.17 no.1
    • /
    • pp.71-77
    • /
    • 1999
  • Phytoplankton communities were investigated 13 times during the period from November, 1995 to December, 1996 in the coastal area of Kori. A total of 162 taxa (including unidentified species) were observed; 120 diatoms, 3 silicoflagellates, 34 dinoflagellates, 2 euglenoids, 1 chlorophyte and 2 unidentified microflagellates. A diatom species, Skeletonema costatum (Greville) Clove dominated all the year round. The standing stocks of phytoplankton ranged from 94 cells/ml in August to 1059 cells/ml in July. The peaks of standing stocks occurred in February and July. The effects of thermal effluent to the phytoplankton communities changed seasonally and might affect increasing the standing stocks where about 1 ∼ 3 km from the discharge of Kori Nuclear Power Plant in autumn and winter. But the effects of thermal effluent must be negative in summer.

  • PDF