• Title/Summary/Keyword: High Burn-up

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Quantitative Evaluation of Criticality According to the Major Influence of Applied with Burnup Credit on Dual-purpose Metal Cask (국내 금속겸용용기의 연소도 이득효과 적용 시 주요영향인자에 따른 정량적 핵임계 평가)

  • Dho, Ho-seog;Kim, Tae-man;Cho, Chun-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.13 no.2
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    • pp.141-154
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    • 2015
  • In general, conventional criticality analysis for spent fuel transport/storage systems have been performed based on the assumption of fresh fuel concerning the potential uncertainties from number density calculations of actinide nuclides and fission products in spent fuel. However, these evaluation methods cause financial losses due to an excessive criticality margin. In order to overcome this disadvantage, many studies have recently been conducted to design and commercialize a transportation and storage cask applied to the Burnup Credit (BUC). This study conducted an assessment to ensure criticality safety for reactor operating parameters, axial burn-up profiles and misload accident conditions, which are the factors that are likely to affect criticality safety when the BUC is applied to the dual-purpose cask under development at the KOrea RADioactive waste agency (KORAD). As a result, it was found that criticality resulting from specific power, changed substantially and relied on conditions of low enrichment and high burn-up. Considering the end effect in the case of high burn-up produced a positive-definite result. In particular, the increment of maximum effective multiplication factors due to misloading was 0.18467, confirming that misload is a factor that must be taken into account when applying the BUC. The results of this study may therefore be utilized as references in developing technologies to apply the BUC to domestic models and operational procedures or preventing any misload accidents during the process of spent fuel loading.

Development of Coolant Flow Simulation System for Nuclear Fuel Test Rigs (핵연료조사리그 냉각수 유동 모의장치 개발)

  • Hong, Jintae;Joung, Chang-Young;Heo, Sung-Ho;Kim, Ka-Hye
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.39 no.1
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    • pp.117-123
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    • 2015
  • To remove heat generated during a burn-up test of nuclear fuels, the heat generation rate of nuclear fuels should be calculated accurately, and a coolant should be circulated in the test loop at an adequate flow rate. HANARO is an open pool-type reactor with an independent test loop for the burn-up test of nuclear fuels. A test rig is installed in the test loop, and a coolant is circulated through the test loop to maintain the temperature of the nuclear fuel rods within a desired temperature during an irradiation test. The components and sensors in the test rig can be broken or malfunction owing to the flow-induced vibration. In this study, a coolant flow simulation system was developed to verify and confirm the soundness of components and sensors assembled in the test rig with a high flow rate of the coolant.

A REVIEW AND INTERPRETATION OF RIA EXPERIMENTS

  • Vitanza, Carlo
    • Nuclear Engineering and Technology
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    • v.39 no.5
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    • pp.591-602
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    • 2007
  • The results of Reactivity-Initiated Accidents (RIA) experiments have been analysed and the main variables affecting the fuel failure propensity identified. Fuel burn-up aggravates the mechanical loading of the cladding, while corrosion, or better the hydrogen absorbed in the cladding as a consequence of corrosion, may under some conditions make the cladding brittle and more susceptible to failure. Experiments point out that corrosion impairs the fuel resistance for RIA transient occurring at cold conditions, whereas there is no evidence of important embrittlement effects at hot conditions, unless the cladding was degraded by oxide spalling. A fuel failure threshold correlation has been derived and compared with experimental data relevant for BWR and PWR fuel. The correlation can be applied to both cold and hot RIA transients, account taken for the lower ductility at cold conditions and for the different initial enthalpy. It can also be used for non-zero power transients, provided that a term accounting for the start-up power is incorporated. The proposed threshold is easy to use and reproduces the results obtained in the CABRI and NSRR tests in a rather satisfactory manner. The behaviour of advanced PWR alloys and of MOX fuel is discussed in light of the correlation predictions. Finally, a probabilistic approach has been developed in order to account for the small scatter of the failure predictions. This approach completes the RIA failure assessment in that after determining a best estimate failure threshold, a failure probability is inferred based on the spreading of data around the calculated best estimate value.

Study of morphology on the Oxidation and the Annealing of High Burn-hp $UO_2$ Spent Fuel (고연소도 사용후 핵연료의 가열산화와 고온가열을 통한 미세조직 변화고찰)

  • Kim Dae Ho;Bang Jae Geun;Yang Yong Sik;Song Keun Woo;Lee Hyung Kwon;Kwon Hyung Moon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.4
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    • pp.301-307
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    • 2005
  • The morphology of the high burnup $UO_2$ spent fuel, which was oxidized and annealed in a PIA (Post Irradiation Annealing) apparatus, has been observed. The high burnup fuel irradiated in Ulchin Unit 2, average rod burnup 57,000 MWd/tU, was transported to the KAERI's PIEF. The test specimen was used with about 200 mg of the spent $UO_2$ fuel fragment of the local burnup 65,000 MWd/tU. This specimen was annealed at $1400^{\circ}C$ for 4hrs after the oxidation for 3hrs to grain boundary using the PIA apparatus in a hot-cell. In order to oxidize the grain boundary, the oxidation temperature increased up to $500^{\circ}C$ and held for 3hrs in the mixed gas (60 ml He and 100 ml STD-air) atmosphere. The amount of 85Kr during the whole test process was measured to know the fission gas release behavior using the online system of a beta counter and a gamma counter. The detailed micro-structure was observed by a SEM to confirm the change of the fuel morphology after this test. As the annealing temperature increased, the fission products were observed to move to the grain surface and grain boundary of the $UO_2$ matrix. This specimen was re-structured through the reduction process, and the grain sizes were distributed from 5 to $10\;{\mu}m$.

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Hydrogen Effect on the Oxidation of Zr-Alloy Claddings under High Temperature (수소화물에 의한 Zr 합금의 고온산화 가속효과)

  • Jung, Yunmock;Ha, Sungwoo;Park, Kwangheon
    • Journal of the Korean institute of surface engineering
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    • v.49 no.4
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    • pp.389-394
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    • 2016
  • The operation method of nuclear power plants is currently changing to high burn-up and long period that can enhance economics and efficiency of the plant. Since nuclear plant operation environment has been becoming severe, the amount of absorbed hydrogen also has increased. Absorbed hydrogen can be fatal securing safety of nuclear fuel cladding in case of Loss of Coolant Accidents(LOCA). In order to examine the impact of hydride on high-temperature oxidation, high-temperature oxidation experiment was performed on normal Zry-4 cladding and on Zry-4 cladding where hydrogen is charged in air pressure steam atmosphere under the $950^{\circ}C$ and $1000^{\circ}C$. According to the results, while oxidation acceleration due to charged hydrogen was not observed prior to breakaway oxidation creation, oxidation began to accelerate in cladding where hydrogens charged as soon as the breakaway oxidation started. If so much hydrogen are charged in the cladding, equiaxial monoclinic phase to unstable of stress is formed and it is presumed that oxidation is accelerated because nearby stress caused a crack in equiaxial phase, and that makes corrosion resistance decline sharply.

Development and Application of High Energy Ignition System Using Plasma (플라즈마 응용 고 에너지 점화 시스템 개발 및 적용)

  • Kang, Hyehyun;Choi, Duwon;Park, Jinil;Lee, Jonghwa;Park, Kyoungseok;Ahn, Jongyoung
    • Transactions of the Korean Society of Automotive Engineers
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    • v.22 no.3
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    • pp.148-156
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    • 2014
  • This study is a follow-up study of "Development of Plasma Ignition System" was presented at the 2013 KSAE spring conference. This study compares lean limit of conventional ignition system with plasma ignition system on constant volume combustion test & Engine Combustion test.

REVIEW AND FUTURE ISSUES ON SPENT NUCLEAR FUEL STORAGE

  • Saegusa, T.;Shirai, K.;Arai, T.;Tani, J.;Takeda, H.;Wataru, M.;Sasahara, A.;Winston, P.L.
    • Nuclear Engineering and Technology
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    • v.42 no.3
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    • pp.237-248
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    • 2010
  • The safety of metal cask and concrete cask storage technology has been verified by CRIEPI through several research programs on demonstrative testing for the interim storage of spent fuel. The results have been reflected in the safety requirements for dry casks issued by NISA/METI (Nuclear and Industrial Safety Agency, Ministry of Economy, Trade and Industry) of the Japanese government. On top of that, spent fuel integrity has been studied by the Japan Nuclear Energy Safety Organization (JNES). This paper reviews these research programs. Future issues include the long-term integrity of cask components and high burn-up spent fuel.

A Study on the Combustion Characteristics of MCFC Offgas Catalytic Combustors (MCFC 배가스용 촉매연소기 연소특성에 관한 연구)

  • Lee, Sang Min;Lee, Younhwa;Ahn, Kook Young;Park, In-Wook
    • 한국신재생에너지학회:학술대회논문집
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    • 2010.06a
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    • pp.132.1-132.1
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    • 2010
  • Anode off-gas of high temperature fuel cells such as MCFC still contain combustible components such as hydrogen, carbon monoxide and hydrocarbon. Thus, it's very important to fully burn anode off-gas and use the generated heat in order to increase system efficiency. In the present study, catalytic combustors have been applied to high temperature MCFC system so that the combustion of anode-off gas can be boosted up. Since the performance of catalytic combustor directly depends on the combustion catalyst, this study has been focused on the experimental investigation on the combustion characteristics of multiple commercial catalysts having different structures and compositions. In order to determine the design conditions of the catalytic combustor, parameters such as inlet temperature, space velocity and excess air ratio have been varied and optimized for combustor design. Results show that $H_2$ in off-gas assists $CH_4$ combustion in a way that it decreases minimum inlet temperature limit and increases maximum space velocity while keeping high fuel conversion efficiency.

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A Comparative Study on Ancient Gagye on Mural Paintings in Korea and China (한국과 중국 고분벽화에 나타난 고대 가계의 비교연구)

  • Yim, Lynn
    • Journal of the Korean Society of Clothing and Textiles
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    • v.36 no.7
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    • pp.778-789
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    • 2012
  • The characteristics of ancient gagye (the cubic hair style which added wigs or other materials to hair) that appeared in mural paintings were compared between Pyongyang and Jian in Goguryeo and the midlands, the northwest region, and the northeast region in China for the same period (Han to Weijin, and Northern and Southern Dynasties). Gagye in Korea and China was classified into circle type, hat type, high-bun type, and multi-bun type; in addition, Han elements, northern race elements, Goguryeo elements, and uniqueness were compared and analyzed according to regional distribution, trend periods, and style characteristics. The Han elements of ancient gagye in Korea and China appeared in the hat type, the high-bun type, and accessories that left the hair down. The northern race elements were found in the circle type and multi-bun type. The uniqueness of Goguryeo elements included a circle from the circle type, a triangle style from the hat type, an up-do style from the high burn type, and simplified hair accessories.