• Title/Summary/Keyword: 방사능 사고

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The language world of dystopia : focusing on the "Fuji-no-shima" and "Gentoshi" of Yoko Tawada. (디스토피아의 언어세계 - 다와다 요코의 「불사의 섬」과 「헌등사」를 중심으로 -)

  • Nam, Sang-wook
    • Cross-Cultural Studies
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    • v.51
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    • pp.213-233
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    • 2018
  • Representing the future of language is a very difficult but important issue, because it signifies a world of language different from the present; at the same time it secures the identity of the present language between the future changed language and the present one. This paper examines the linguistic world of dystopia, focusing on the "Fuji-no-shima" and "Gentoshi" of Yoko Tawada. First of all, "Fuji-no-shima" shows that, for Yoko Tawada, who was crossing the border between German and Japanese as a bilingual writer, the accidental Fukushima nuclear power generation in 2011 was accepted as the destruction of verbal order between signifiant and $signifi{\acute{e}}$, due to physical changes caused by radiation leaks. "Gentoshi" tells that human ties can be maintained through language activities that can capture multiple meanings, even in a world where traditional language order is destroyed through a policy of seclusion. From the above discussion, the novel Distopia, can actually be called Utopia as long as humans rely on the power of various languages to sustain it.

Analysis of Internal Pressure Capacity of Modular Containment Structure for Small Modular Reactor (소형 원자로용 모듈화 격납구조의 내압성능 분석)

  • Park, Woo-Ryong;Yhim, Sung-Soon
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.20 no.8
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    • pp.362-370
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    • 2019
  • The internal pressure capacity of a modular containment structure requires analysis to prevent the release of radioactive material in the case of an accident. To analyze the capacity, FEM models were prepared while considering the tendon arrangements and the contact surfaces between precast concrete modules, and then static analyses were carried out. The changing characteristics in the displacement and stress under step-wise loading were analyzed, along with the effects of selected parameters. For comparison, the capacity of a monolithic containment structure was also analyzed. Parametric analyses were done to suggest ranges of parameters such as the tendon force, tendon spacing, tendon location in concrete thickness direction, friction coefficient, and concrete thickness. The tendon force and frictional force provide a combined effect between contact surfaces of modules. The same level of internal pressure capacity can be secured even in the modular containment structure as in the monolithic containment structure by increasing the tendon force with additional tendons.

Comparison of Perception Differences About Nuclear Energy in 4 East Asian Country Students: Aiming at $10^{th}$ Grade Students who Participated in Scientific Camps, from Four East Asian Countries: Korea, Japan, Taiwan, and Singapore (동아시아 4개국 학생들의 핵에너지에 대한 인식 비교: 과학캠프에 참가한 한국, 일본, 대만, 싱가포르 10학년 학생들을 대상으로)

  • Lee, Hyeong-Jae;Park, Sang-Tae
    • Journal of The Korean Association For Science Education
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    • v.32 no.4
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    • pp.775-788
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    • 2012
  • This study was done at a scientific camp sponsored by Nara Women's University Secondary School, Japan. In this school, $10^{th}$ grade students from 4 East Asian countries: Korea, Japan, Taiwan, and Singapore, participated. We made a research on students' perceptions about nuclear energy. Sample populations include 77 students in total, with 12 Korean, 46 Japanese, 9 Taiwanese and 10 Singaporean students. Overall perceptions comparison about nuclear energy shows average values from the order of highest Korea, Taiwan, Singapore, and to lowest, Japan. We implemented a T-test to identify perception differences about nuclear energy, with one group that include 3 countries (Korea, Taiwan and Singapore) and another group that includes all the Japanese students. T-test results of perceptions about nuclear energy shows students from the 3 countries of Korea, Taiwan and Singapore having higher average than Japanese students. (p<.05). Korean average scores regarding overall perceptions about nuclear energy show as the highest in all 4 East Asian countries and also highest in all subcategories. On the contrary in Japan, they have lower and negative perceptions of nuclear energy. In spite of these facts, perceptions of Japanese students about nuclear energy seem lowest and negative mainly because of the recent Fukushima nuclear power plant disaster, caused by the tsunami and its subsequent damages and fears of radiation leaks, etc. This shows that negative information about future disasters and its resulting damages like the Chernobyl nuclear accident could influence more on people's risk perception than general information like nuclear energy-related technologies or the news that the plant is operating normally, etc. Even if the possibility of this kind of accident is very low, just one accident could bring abnormal risks to technology itself. This strong signal makes negative image and strengthens its perceptions to the people. This could bring a stigma about nuclear energy. This study shows that Government's policy about the highest priority for nuclear energy safety is most important. As long as such perception and decision are fixed, we found that it might not be easy to get changed again because they were already fortified and maintained.

A Study of the Improvement Plan and Real Condition Estimation of Fire Protection Safety Management for Power Plants in Korea (국내발전소 소방안전관리 운영실태조사 및 개선방안에 관한 연구)

  • Kang, Gil-Soo;Choi, Jae-wook
    • Fire Science and Engineering
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    • v.31 no.2
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    • pp.61-73
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    • 2017
  • The Fukushima Nuclear Disaster in 2011 and California Power Failure in 2001 are examples of the importance of the power plant safety management that caused huge national loss with a power-related mass casualty incident. In a situation where humans cannot live without electricity, efforts to strengthen the systematic firefighting safety management in power plants that produce electricity with large amounts of hazardous materials as fuel, such as nuclear energy, coal and gas, are essential to protect life and prevent property loss and stable economic growth from fire explosion accident or radiation leak due to the negligence of safety management and natural disasters such as earthquakes, which has recently become an issue. This study examined the operating situation of firefighting safety management in power plants with firefighting officials employed by five power generation companies including Korea Southern Power Co., Ltd. and Korea Hydro & Nuclear Power Co. Ltd., which are in charge of the domestic power supply. As a result, for the systematic firefighting safety management of power plants, improvement plans were drawn, including the development of an effective business manual and a comprehensive management system, the substantiality of firefighting safety education, and the strengthening of seismic designs to prepare for earthquakes.

Development of the IRIS Collimator for the Portable Radiation Detector and Its Performance Evaluation Using the MCNP Code (IRIS형 방사선검출기 콜리메이터 제작 및 MCNP 코드를 이용한 성능평가)

  • Ji, Young-Yong;Chung, Kun Ho;Lee, Wanno;Choi, Sang-Do;Kim, Change-Jong;Kang, Mun Ja;Park, Sang Tae
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.13 no.1
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    • pp.55-61
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    • 2015
  • When a radiation detector is applied to the measurement of the radioactivity of high-level of radioactive materials or the rapid response to the nuclear accident, several collimators with the different inner radii should be prepared according to the level of dose rate. This makes the in-situ measurement impractical, because of the heavy weight of the collimator. In this study, an IRIS collimator was developed so as to have a function of controlling the inner radius, with the same method used in optical camera, to vary the attenuation ratio of radiation. The shutter was made to have the double tungsten layers with different phase angles to prevent the radiation from penetrating owing to the mechanical tolerance. The performance evaluation through the MCNP code was conducted by calculating the attenuation ratio according to the inner radius of the collimator. The attenuation ratio was marked on the outer scale ring of the collimator. It is expected that when a radiation detector with the IRIS collimator is used for the in-situ measurement, it can change the attenuation ratio of the incident photon to the detector without replacing the collimator.

Contamination of Chinese Cabbage with $^{85}Sr$, $^{103}Ru$ and $^{134}Cs$ Related to Time of Foliar Application ($^{85}Sr$, $^{103}Ru$, $^{134}Cs$의 엽면처리 시기에 따른 배추의 방사능 오염)

  • Choi, Yong-Ho;Lim, Kwang-Muk;Park, Hyo-Guk;Lee, Won-Yun;Lee, Chang-Woo
    • Journal of Radiation Protection and Research
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    • v.23 no.4
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    • pp.219-227
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    • 1998
  • A solution containing $^{85}Sr$, $^{103}Ru$ and $^{134}Cs$ was applied to Chinese cabbage in a greenhouse via foliar spraying at 5 different times during its growth. Interception of the applied activity by plant showed no difference among radionuclides and increased with decreasing time interval between application and harvest. The maximum interception factor observed was 0.87. Percentages of the intercepted activity remaining in the whole leaves at harvest varied $16{\sim}58%$ for $^{85}Sr$, $15{\sim}73%$ for $^{103}Ru$ and $33{\sim}64%$ for $^{134}Cs$, with application time and those for the inner leaves (without 6 outmost leaves) varied $2{\sim}35%$, $0.4{\sim}46%$ and $14{\sim}40%$, respectively. It was demonstrated that rain plays an important role in weathering loss of the activity. Tying the upper end of the plant prior to the last application lowered interception and remaining activity in the inner leaves by factors of $3{\sim}4$. Present results can be referred to in predicting the radionuclide concentration in Chinese cabbage and deciding counter-measures at the time of an accidental release from the nuclear installation.

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Reliability Analysis Method for Concrete Containment Structures (콘크리트 차폐(遮蔽) 구조물(構造物)의 신뢰성(信賴性) 해석방법(解析方法))

  • Han, Bong Koo;Chang, Sung Pil
    • KSCE Journal of Civil and Environmental Engineering Research
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    • v.10 no.1
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    • pp.9-16
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    • 1990
  • The safety of concrete nuclear containment structures should be secured against all kinds of loading due to various natural disasters or extraordinary accidental loads. The current design criteria of concrete containment structures are not based on the reliabillty-based design concept but rely on the conventional design concept. In this paper, a probabillty-based reliability analysis were proposed based on a FEM-based random vibration analysis and serviceability limit state of structures. The limit state model defined for the study is a serviceability limit state in terms of the more realistic crack failure that might cause the emission of radioactive materials, and the results are compared with those of the strength limit state. More accurate reliability analyses under various dynamic loads such as earthquake loads were made possible by incorporation the FEM and random vibration theory, which is different from the conventional reliability analysis method. The uncertainties in loads and resistance available in Korea and the refernces were adapted to the situation of Korea, and especially in the case of earthquake, the design earthquake was assessed based on the available re ports on probabilistic description of earthquake ground acceleration in the Korea peninsula.

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Radiation Shielding Analysis on The Spent Fuel Storage Facility for the Extended Fuel Cycle (장주기(長週期) 핵연료(核燃料) 저장시설(貯藏施設)에서의 방사선차폐해석(放射線遮蔽解析))

  • Lee, Tae-Young;Ha, Chung-Woo;Yook, Chong-Chul
    • Journal of Radiation Protection and Research
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    • v.9 no.2
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    • pp.90-96
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    • 1984
  • Estimated dose rates in spent fuel pool storage with the extended fuel cycle core management were reviewed and compared with design limit after calculation with the aid of DLC-23/CASK(22 n, 18 g) nuclear data and ANISN code. Radioactivity and gamma spectrum within spent fuel assemblies were calculated with ORIGEN code by extended fuel cycle model. In the calculation of dose rate, the fuel pool geometry was assumed to be infinite slab. Also, composition materials and radiation source within assemblies which are being stored in pool storage were assumed to be uniformly distributed throughout all the assemblies. As a result of culculation of dose rate from stored assemblies and waterborne radionuclides in pool water, the calculated dose rates appear to be lower than design basis limit under normal condition as well as abnormal condition.

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Passive autocatalytic recombiner guide structure considering ambient flow (분위기 유동을 고려한 PAR 가이드 구조에 관한 연구)

  • Ryu, Myeong-Rok;Park, Kweon-Ha
    • Journal of Advanced Marine Engineering and Technology
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    • v.41 no.4
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    • pp.302-309
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    • 2017
  • If a hydrogen explosion occurs in a containment building, its multiplex defense wall may be destroyed and a large amount of radioactive material may be released. The hydrogen occurred interacting with melting fuel rods must be effectively controlled and removed. however, the countermeasures for reducing explosion risk are difficult to carry out, due owing to the various variety of accident scenarios causes and the irregularity of hydrogen distribution and behavior. In this study, We examine the guide structures while considering the ambient flows, in order to improve the efficiency of PAR the widely used Passive Autocatalytic Recombiner(PAR). We simulate the fluid behavior and the hydrogen reduction rate were simulated when a guide is attached to the two-step catalyst PAR. For an upward flow, the consisting of a height of 150mm, a gap of 0mm, and a performs $60^{\circ}$ showed the best. In contrast, for a sideways flow, a consisting of the height of 150mm, a gap of 100mm, and a performs $60^{\circ}$ showed the best in the case of side ward flow. for a downward flow, a consisting of the height of 50mm and a directly attached guide produce the best in the case of down ward flow results.

Effect of Oral Ingestion of Chitosan and Alginate on the Removal of Orally Ingested Radiostrontium ($^{85}Sr$) in Mice (마우스에서 경구투여한 방사성스트론튬의 제거에 대한 경구투여 카이토산과 알긴산의 효과)

  • Kim, Hee-Kyung;Kim, Kwang-Yoon;Bom, Hee-Seung;Choi, Keun-Hee;Kim, Ji-Yeul
    • The Korean Journal of Nuclear Medicine
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    • v.27 no.1
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    • pp.130-134
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    • 1993
  • Radiostrontium is one of fallouts. It can be absorbed through intestine and causing radiation injury to bones. The purpose of this study is to evaluate the inhibitory effect of 10% chitosan (water soluble and insoluble) and 10% alginate (water soluble and insoluble) on radiostrontium adsorption. Water soluble and insoluble chitosans and alginates were given to 10 NIH male mice in each group for 7 days. At the 7th day, 74 MBq of $^{85}Sr$ were given through orogastric tube. Chitosans and alginates were given for additional 7 days. During the 7 days, radioactivities of feces were counted daily. Finally animals were sacrificed, and radioactivities of bones were counted. Fecal excretion was significantly higher in chitosan and alginate group as compared to control from the 1st day (p < 0.01). Water soluble chitosan group showed highest fecal excretion. Bony retention was significantly lower in the treated group than the control (p < 0.01). There was no difference among treated groups. In conclusion, both water soluble and insoluble chitosans and alginates were effective agents on lowering orally ingested radiostrontium ($^{85}Sr$).

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