• Title/Summary/Keyword: Nuclear power plant accident

Search Result 439, Processing Time 0.03 seconds

Clonal plant as experimental organisms - DNA mutation rate evaluation in the radiation contaminated area of Fukushima Daiichi NPP accident

  • KANEKO, Shingo
    • 한국자원식물학회:학술대회논문집
    • /
    • 한국자원식물학회 2018년도 추계학술대회
    • /
    • pp.25-25
    • /
    • 2018
  • The Fukushima Daiichi Nuclear Power Plant accident in March 2011 caused severe radioactive contamination in the surrounding environment. Since the accident, much attention has been paid to the biological and genetic consequences of organism inhabiting the contaminated area. The effect of radiation exposure on genetic mutation rates is little known, especially for low doses and in situ conditions. Evaluating DNA mutation by low levels of radiation dose is difficult due to the rare mutation event and lack of sequence information before the accident. In this study, correlations with air dose levels and somatic DNA mutation rates were evaluated using Next Generation Sequencer for the clonal plant, Phyllostachys edulis. This bamboo is known to spread an identical clone throughout Japan, and it has the advantage that we can compare genetic mutation rate among identical clone growing different air dose levels. We collected 94 samples of P. edulis from 14 sites with air dose rates from $0.04{\sim}7.80{\mu}Gy/h$. Their clonal identity was confirmed by analysis using 24 microsatellite markers, and then, sequences among samples were compared by MIG sequence. The sequence data were obtained from 2,718 loci. About ~200,000 bp sequence (80 bp X 2,718 loci) were obtained for each sample, and this corresponds to about 0.01% of the genome sequence of P. edulis. In these sequences, 442 loci showed polymorphism patterns including recent origin mutation, old mutation, and sequence errors. The number of mutations per sample ranged from 0 to 13, and did not correlate with air dose levels. This result indicated that DNA mutations have not accumulated in P. edulis living in the air doses levels less than $10{\mu}Gy/h$. Our study also suggests that mutation rates can be assessed by selecting an appropriate experimental approach and analyzing with next generation sequencer.

  • PDF

원전 비상 노심냉각계통 배관 열성층화 현상 규명을 위한 실험적 연구 (Experimental Research for Identification of Thermal Stratification Phenomena in The Nuclear Powerplant Emergency Core Coolant System(ECCS).)

  • 송도인;최영돈;박민수
    • 대한기계학회:학술대회논문집
    • /
    • 대한기계학회 2001년도 추계학술대회논문집B
    • /
    • pp.735-740
    • /
    • 2001
  • In the nuclear power plant, emergency core coolant system(ECCS) is furnished at reactor coolant system(RCS) in order to cool down high temperature water in case of emergency. However, in this coolant system, it occurs thermal stratification phenomena in case that there is the mixing of cooling water and high temperature water due to valve leakage in ECCS. This thermal stratification phenomena raises excessive thermal stresses at pipe wall. Therefore, this phenomena causes the accident that reactor coolant flows in reactor containment in the nuclear power plant due to the deformation of pipe and thermal fatigue crack(TFC) at the pipe wall around the place that it exists. Hence, in order to fundamental identification of this phenomena, it requires the experimental research of modeling test in the pipe flow that occurs thermal stratification phenomena. So, this paper models RCS and ECCS pipe arrangement and analyzes the mechanism of thermal stratification phenomena by measuring of temperature in variance with leakage flow rate in ECCS modeled pipe and Reynold number in RCS modeled pipe. Besides, results of this experiment is compared with computational analysis which is done in advance.

  • PDF

냉각재 상실사고 후 격납건물내의 이상유동 연구 (A Study on the Two Phase Flow in the Floor of Containment Building after a Loss of Coolant Accident)

  • 배진효;박만흥;고철균;이재헌
    • 대한기계학회논문집B
    • /
    • 제23권10호
    • /
    • pp.1274-1284
    • /
    • 1999
  • The Regulatory Guide 1.82 recommends an analysis of hydraulic performance for sump of ECCS (Emergency Core Cooing System) when LOCA(Loss of Coolant Accident) occurs in a nuclear power plant. The present study deals with 3-dimensional, unsteady, turbulent and two-phase flow simulation to examine the behavior of mixture of reactor coolant and debris near the floor of containment building in conjunction with appropriate assumptions. The dispersed solid model has been adjusted to the interfacial momentum transfer between reactor coolant and debris. According to the results, the counterclockwiserecirculation zone had been formed in the region between sump and connection aisle about 376 second after LOCA occurs. The debris thickness accumulated on a sump screen periodically increases or decreases up to 2000 second, afterwards its peak decreases.

신뢰성에 관한 고찰 (A Study on Reliability)

  • 이근희
    • 산업경영시스템학회지
    • /
    • 제2권2호
    • /
    • pp.1-4
    • /
    • 1979
  • In order to cope with the violent environment of surrounding enterprises, development of new products, advance to other industry field, unification or abolition of factories and rationlization of labor are needed. But production process being made quality and using process after shipment are the things that we have to think about, first of all and to practice always. Insurance problem of reliability, that is, the positive quality maintenance that has being presented many debate issues recently, will be studied. The accident of nuclear power-plant in America, in connection with reliability maintenance and human engineering, will be analyzed. But as its accident details is not announced, in this study, it is a sort of method of methodology to be studied this paper rather than studying the fact of the accident. Therefore this study will be done as follows, For reliability study. 1. Investigation of problems. 2. Quality maintenance activity and reliability maintenance activity 3. Reliability acquisition in production process, 4. Reliability maintenance after shipment. 5. Conclusion. In addition to stating above, it is sure that liberalization of trade, interchange between nations and strengthening of international competition ability, etc. need high quality. But possibility that quality maintenance or reliability aquisition needs understanding and cooperation of consumer, will be stated.

  • PDF

Development of RADCON and Establishments of Its Related System

  • Kim, Kuk-Ki;Lee, Kun-Jai;Park, Won jong
    • 한국원자력학회:학술대회논문집
    • /
    • 한국원자력학회 1996년도 춘계학술발표회논문집(4)
    • /
    • pp.51-56
    • /
    • 1996
  • In a NNP (Nuclear Power Plant) severe accident, radionuclides are dispersed into the air. The official regulatory institute, KINS (Korea Institute of Nuclear Safety), has been authorized and developing Computerized technical Advisory system for the Radiological Emergency preparedness (CARE). In this paper, in line with the CARE system, we presented the result of a modularized intermediate-level emergency dose assessment computer code. The RADCON (RADiological CONsequence analysis) version 3.0, which is operable on PC, is developed for simulating emergency situation by considering continuous washout phenomena, and provide a function of effective emergency planning. The source files are coded by using C language in order to increase the compatibility with the other computer system and modularized to adjust the functions and characteristics of each module fer easy understanding and further modification.

  • PDF

원자로 제어봉과 결합된 하이브리드 히트파이프의 CFD 해석 (CFD Analysis of a Concept of Nuclear Hybrid Heat Pipe with Control Rod)

  • 정영신;김경모;김인국;방인철
    • 한국유체기계학회 논문집
    • /
    • 제17권6호
    • /
    • pp.109-114
    • /
    • 2014
  • After the Fukushima accident in 2011, it was revealed that nuclear power plant has the vulnerability to SBO accident and its extension situation without sufficient cooling of reactor core resulting core meltdown and radioactive material release even after reactor shutdown. Many safety systems had been developed like PAFS, hybrid SIT, and relocation of RPV and IRWST as a part of steps for the Fukushima accident, however, their applications have limitation in the situation that supply of feedwater into reactor is impossible due to high pressure inside reactor pressure vessel. The concept of hybrid heat pipe with control rod is introduced for breaking through the limitation. Hybrid heat pipe with control rod is the passive decay heat removal system in core, which has the abilities of reactor shutdown as control rod as well as decay heat removal as heat pipe. For evaluating the cooling performance hybrid heat pipe, a commercial CFD code, ANSYS-CFX was used. First, for validating CFD results, numerical results and experimental results with same geometry and fluid conditions were compared to a tube type heat pipe resulting in a resonable agreement between them. After that, wall temperature and thermal resistances of 2 design concepts of hybrid heat pipe were analyzed about various heat inputs. For unit length, hybrid heat pipe with a tube type of $B_4C$ pellet has a decreasing tendency of thermal resistance, on the other hand, hybrid heat pipe with an annular type $B_4C$ pellet has an increasing tendency as heat input increases.

A Systems Engineering Approach for Predicting NPP Response under Steam Generator Tube Rupture Conditions using Machine Learning

  • Tran Canh Hai, Nguyen;Aya, Diab
    • 시스템엔지니어링학술지
    • /
    • 제18권2호
    • /
    • pp.94-107
    • /
    • 2022
  • Accidents prevention and mitigation is the highest priority of nuclear power plant (NPP) operation, particularly in the aftermath of the Fukushima Daiichi accident, which has reignited public anxieties and skepticism regarding nuclear energy usage. To deal with accident scenarios more effectively, operators must have ample and precise information about key safety parameters as well as their future trajectories. This work investigates the potential of machine learning in forecasting NPP response in real-time to provide an additional validation method and help reduce human error, especially in accident situations where operators are under a lot of stress. First, a base-case SGTR simulation is carried out by the best-estimate code RELAP5/MOD3.4 to confirm the validity of the model against results reported in the APR1400 Design Control Document (DCD). Then, uncertainty quantification is performed by coupling RELAP5/MOD3.4 and the statistical tool DAKOTA to generate a large enough dataset for the construction and training of neural-based machine learning (ML) models, namely LSTM, GRU, and hybrid CNN-LSTM. Finally, the accuracy and reliability of these models in forecasting system response are tested by their performance on fresh data. To facilitate and oversee the process of developing the ML models, a Systems Engineering (SE) methodology is used to ensure that the work is consistently in line with the originating mission statement and that the findings obtained at each subsequent phase are valid.

공정열 및 수소생산을 위한 초고온가스로 열평형 분석 (Heat balance analysis for process heat and hydrogen generation in VHTR)

  • 박소영;허균영;유연재;이상일
    • 에너지공학
    • /
    • 제25권4호
    • /
    • pp.85-92
    • /
    • 2016
  • 초고온가스로는 열출력 밀도가 낮아 노심용융의 가능성이 낮으며, 냉각재 상실사고 시 수소 발생 등으로 인한 폭발의 위험도 없다. 안전성 측면의 장점과 더불어 냉각재를 초고온으로 만들어 전력생산이외에 산업시설용 공정열로의 응용도 가능하다. 본 논문에서는 초고온가스로를 일차계통으로 하고, 전력 및 공정열 공급이 가능한 이차계통의 개념 설계를 담고 있다. 기존에 NGNP(Next Generation Nuclear Part)에서 제안한 350 MW 열출력 원자로 모델을 기반으로 수소생산 루프와는 별도로 전력생산을 위한 300 MW의 열에너지를 중간열교환기를 통해 이차계통으로 전달하는 참조모델을 개발하고, 이를 열역학적 측면에서 분석하였으며 이차계통 각 지점에서 주요 설계변수에 따른 효율분석과 최적화개념 연구를 수행하였다.

What Can Radiation Protection Experts Contribute to the Issue of the Treated Water Stored in the Damaged Fukushima Daiichi Nuclear Power Plant?

  • Yamaguchi, Ichiro
    • Journal of Radiation Protection and Research
    • /
    • 제46권1호
    • /
    • pp.24-31
    • /
    • 2021
  • Decommissioning efforts are underway at the reactor where the accident occurred, namely the damaged Tokyo Electric Power Company (TEPCO) Fukushima Daiichi Nuclear Power Plant (FDNPP). However, a large amount of groundwater flowing into the site has become contaminated with radioactive substances and is stored in tanks on site, which has hampered the decommissioning work. Although the inflow of groundwater has been greatly reduced through measures such as the construction of frost walls, approximately 170 ㎥ of water treated by the Advanced Liquid Processing System (ALPS) is being stored in tanks, each day. The tanks used to store this treated water are expected to become full by around the summer of 2022. It is not easy to get people to understand the efforts of all concerned parties, and providing clear information to these concerned parties is also a challenge. Questions have also been raised regarding whether other alternatives have been fully explored in the ALPS subcommittee. Some people have commented that the answers to the questions raised regarding the biological effects of tritium transmutation are inadequate. Some suspect that the answers are too detailed and incomprehensible, and that the respondents may be manipulating the public with some malicious intent. In any case, each possible plan presents both advantages and disadvantages, depending on the people who are involved. That makes it an ethical and vexing issue that can sway decisions, as perspectives change. While the environmental release plan is scientifically safe, it may represent a painful alternative. On the other hand, a more careful and imaginative approach to the idea of continued storage in tanks or other forms of storage may reveal some troublesome hidden disadvantages. Under these circumstances, experts must be prepared to answer people's questions in a comprehensive and robust manner.

시사 다큐멘터리 프로그램이 수용자의 정치적 사회적 인식에 미치는 영향 - KBS 재난 다큐멘터리, <현장르포, 후쿠시마의 진실>을 중심으로 (Effect of current documentary on viewer's political & social recognition - focused on KBS disaster documentary, )

  • 박덕춘
    • 디지털융복합연구
    • /
    • 제14권12호
    • /
    • pp.463-470
    • /
    • 2016
  • 본 연구는 미디어 효과 연구로서, 후쿠시마 원전 사고에 의해 폭넓게 확산되고 있는 방사능 오염 실태를 취재한 시사 다큐멘터리의 시청이 국내 수용자의 정치적, 사회적 인식에 어떤 영향을 미치는지 실험을 통해 살펴본 연구이다. 그동안의 미디어 효과에 관한 선행 연구들은 TV나 신문 인터넷 등의 뉴스 콘텐츠가 수용자에게 미치는 영향을 살펴보고 있다. 그러나 이들 미디어의 뉴스 콘텐츠 못지않게 다양한 주제를 심층 분석하여 수용자들에게 깊이 있는 정보를 제공하고 있는 TV 시사다큐멘터리를 대상으로 한 수용자 효과 연구는 매우 제한적이며, 특히 지구 환경에 큰 영향을 미치고 있는 방사능 오염을 주제로 한 재난 다큐멘터리가 수용자에 미치는 영향에 관한 연구는 찾아보기 어렵다. 따라서 본 연구에서는 후쿠시마 원전사고에 의한 방사능 오염문제를 집중적으로 보도한 재난 다큐멘터리가 수용자의 정치적, 사회적 인식에 미치는 영향을 살펴보기 위해 실험연구를 수행하였다. 분석결과 시사다큐멘터리를 시청한 피험자들은 시사다큐멘터리를 시청하지 않은 피험자들보다 야당의 지지도가 높았으며, 노후 원전문제를 더 심각하게 인식하여 더 적극적으로 폐기를 주장하는 경향이 있었고, 원전의 추가 건설을 더 적극적으로 반대하는 경향이 있었다.