• 제목/요약/키워드: $g^*$-open sets

검색결과 24건 처리시간 0.02초

다목적실용위성 3A 영상 자료의 지표 반사도 성과 검증: RadCalNet Baotou(BTCN) 자료 적용 사례 (Validation of Surface Reflectance Product of KOMPSAT-3A Image Data: Application of RadCalNet Baotou (BTCN) Data)

  • 김광섭;이기원
    • 대한원격탐사학회지
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    • 제36권6_2호
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    • pp.1509-1521
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    • 2020
  • 다목적실용위성(KOMPSAT-3A: Korea Multi-Purpose Satellite 3A)으로부터 산출된 지표 반사도 성과의 검정 작업을 위하여 분광 반사도 측정값을 제공하고 있는 포털인 Radiometric Calibration Network(RadCalNet)에서 제공하는 4 개의 사이트 자료 중에서 중국 바오터우(Baotou: BTCN) 데이터를 이용한 실험을 수행하였다. 실험을 위한 반사도 성과는 대기 반사도와 지표 반사도를 일괄적으로 처리할 수 있도록 재설계하고 구현한 오픈소스 Orfeo ToolBox(OTB)의 확장 프로그램(Extension)을 이용하여 생성하였다. 절대 대기 보정에 적용되는 두 가지의 센서 모델 변수를 고려하여 2016년, 2017년, 2018년 자료 1개씩 총 3개의 영상 자료를 실험에 적용하였다. 한편 각각 USGS LaSRC 알고리즘과 SNAP Sen2Cor 프로그램을 이용하여 Landsat-8과 Sentinel-2B 영상정보로부터 산출한 반사도 성과와의 비교 검증 작업을 수행하여 센서 별 차이를 확인하고자 하였다. 대기 반사도와 지표 반사도를 대상으로 절대 대기 보정을 위한 필수 입력 값인 Gain과 Offset에 대한 센서 모델 변수 값을 적용한 결과로, 2019년에 발표된 변수 값을 사용한 성과에 비하여 2017년 변수 값을 사용한 성과가 RadCalNet BTCN 자료에 비교적 잘 부합되는 것으로 나타났다. RadCalNet BTCN 자료를 기준으로 KOMPSAT-3A 영상정보의 지표 반사도 성과와의 차이는 밴드 별로 B 밴드(-0.031 ~ 0.034), G 밴드(-0.001 ~ 0.055), R 밴드(-0.072 ~ 0.037), NIR 밴드(-0.060 ~ 0.022)로 일치도가 높은 것으로 나타났고, Landsat-8 영상과 Sentinel-2B 영상의 지표 반사도의 경우도 KOMPSAT-3A 영상의 지표 반사도 성과의 정확도와 유사한 수준인 것으로 나타났다. 이번 연구 결과는 고해상도 위성에서 지표 반사도 값에 대한 분석 대기 데이터(Analysis Ready Data: ARD) 적용 가능성을 확인한 것에 의미가 있다.

APPLICATION OF FUZZY SET THEORY IN SAFEGUARDS

  • Fattah, A.;Nishiwaki, Y.
    • 한국지능시스템학회:학술대회논문집
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    • 한국퍼지및지능시스템학회 1993년도 Fifth International Fuzzy Systems Association World Congress 93
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    • pp.1051-1054
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    • 1993
  • The International Atomic Energy Agency's Statute in Article III.A.5 allows it“to establish and administer safeguards designed to ensure that special fissionable and other materials, services, equipment, facilities and information made available by the Agency or at its request or under its supervision or control are not used in such a way as to further any military purpose; and to apply safeguards, at the request of the parties, to any bilateral or multilateral arrangement, or at the request of a State, to any of that State's activities in the field of atomic energy”. Safeguards are essentially a technical means of verifying the fulfilment of political obligations undertaken by States and given a legal force in international agreements relating to the peaceful uses of nuclear energy. The main political objectives are: to assure the international community that States are complying with their non-proliferation and other peaceful undertakings; and to deter (a) the diversion of afeguarded nuclear materials to the production of nuclear explosives or for military purposes and (b) the misuse of safeguarded facilities with the aim of producing unsafeguarded nuclear material. It is clear that no international safeguards system can physically prevent diversion. The IAEA safeguards system is basically a verification measure designed to provide assurance in those cases in which diversion has not occurred. Verification is accomplished by two basic means: material accountancy and containment and surveillance measures. Nuclear material accountancy is the fundamental IAEA safeguards mechanism, while containment and surveillance serve as important complementary measures. Material accountancy refers to a collection of measurements and other determinations which enable the State and the Agency to maintain a current picture of the location and movement of nuclear material into and out of material balance areas, i. e. areas where all material entering or leaving is measurab e. A containment measure is one that is designed by taking advantage of structural characteristics, such as containers, tanks or pipes, etc. To establish the physical integrity of an area or item by preventing the undetected movement of nuclear material or equipment. Such measures involve the application of tamper-indicating or surveillance devices. Surveillance refers to both human and instrumental observation aimed at indicating the movement of nuclear material. The verification process consists of three over-lapping elements: (a) Provision by the State of information such as - design information describing nuclear installations; - accounting reports listing nuclear material inventories, receipts and shipments; - documents amplifying and clarifying reports, as applicable; - notification of international transfers of nuclear material. (b) Collection by the IAEA of information through inspection activities such as - verification of design information - examination of records and repo ts - measurement of nuclear material - examination of containment and surveillance measures - follow-up activities in case of unusual findings. (c) Evaluation of the information provided by the State and of that collected by inspectors to determine the completeness, accuracy and validity of the information provided by the State and to resolve any anomalies and discrepancies. To design an effective verification system, one must identify possible ways and means by which nuclear material could be diverted from peaceful uses, including means to conceal such diversions. These theoretical ways and means, which have become known as diversion strategies, are used as one of the basic inputs for the development of safeguards procedures, equipment and instrumentation. For analysis of implementation strategy purposes, it is assumed that non-compliance cannot be excluded a priori and that consequently there is a low but non-zero probability that a diversion could be attempted in all safeguards ituations. An important element of diversion strategies is the identification of various possible diversion paths; the amount, type and location of nuclear material involved, the physical route and conversion of the material that may take place, rate of removal and concealment methods, as appropriate. With regard to the physical route and conversion of nuclear material the following main categories may be considered: - unreported removal of nuclear material from an installation or during transit - unreported introduction of nuclear material into an installation - unreported transfer of nuclear material from one material balance area to another - unreported production of nuclear material, e. g. enrichment of uranium or production of plutonium - undeclared uses of the material within the installation. With respect to the amount of nuclear material that might be diverted in a given time (the diversion rate), the continuum between the following two limiting cases is cons dered: - one significant quantity or more in a short time, often known as abrupt diversion; and - one significant quantity or more per year, for example, by accumulation of smaller amounts each time to add up to a significant quantity over a period of one year, often called protracted diversion. Concealment methods may include: - restriction of access of inspectors - falsification of records, reports and other material balance areas - replacement of nuclear material, e. g. use of dummy objects - falsification of measurements or of their evaluation - interference with IAEA installed equipment.As a result of diversion and its concealment or other actions, anomalies will occur. All reasonable diversion routes, scenarios/strategies and concealment methods have to be taken into account in designing safeguards implementation strategies so as to provide sufficient opportunities for the IAEA to observe such anomalies. The safeguards approach for each facility will make a different use of these procedures, equipment and instrumentation according to the various diversion strategies which could be applicable to that facility and according to the detection and inspection goals which are applied. Postulated pathways sets of scenarios comprise those elements of diversion strategies which might be carried out at a facility or across a State's fuel cycle with declared or undeclared activities. All such factors, however, contain a degree of fuzziness that need a human judgment to make the ultimate conclusion that all material is being used for peaceful purposes. Safeguards has been traditionally based on verification of declared material and facilities using material accountancy as a fundamental measure. The strength of material accountancy is based on the fact that it allows to detect any diversion independent of the diversion route taken. Material accountancy detects a diversion after it actually happened and thus is powerless to physically prevent it and can only deter by the risk of early detection any contemplation by State authorities to carry out a diversion. Recently the IAEA has been faced with new challenges. To deal with these, various measures are being reconsidered to strengthen the safeguards system such as enhanced assessment of the completeness of the State's initial declaration of nuclear material and installations under its jurisdiction enhanced monitoring and analysis of open information and analysis of open information that may indicate inconsistencies with the State's safeguards obligations. Precise information vital for such enhanced assessments and analyses is normally not available or, if available, difficult and expensive collection of information would be necessary. Above all, realistic appraisal of truth needs sound human judgment.

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COATED PARTICLE FUEL FOR HIGH TEMPERATURE GAS COOLED REACTORS

  • Verfondern, Karl;Nabielek, Heinz;Kendall, James M.
    • Nuclear Engineering and Technology
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    • 제39권5호
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    • pp.603-616
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    • 2007
  • Roy Huddle, having invented the coated particle in Harwell 1957, stated in the early 1970s that we know now everything about particles and coatings and should be going over to deal with other problems. This was on the occasion of the Dragon fuel performance information meeting London 1973: How wrong a genius be! It took until 1978 that really good particles were made in Germany, then during the Japanese HTTR production in the 1990s and finally the Chinese 2000-2001 campaign for HTR-10. Here, we present a review of history and present status. Today, good fuel is measured by different standards from the seventies: where $9*10^{-4}$ initial free heavy metal fraction was typical for early AVR carbide fuel and $3*10^{-4}$ initial free heavy metal fraction was acceptable for oxide fuel in THTR, we insist on values more than an order of magnitude below this value today. Half a percent of particle failure at the end-of-irradiation, another ancient standard, is not even acceptable today, even for the most severe accidents. While legislation and licensing has not changed, one of the reasons we insist on these improvements is the preference for passive systems rather than active controls of earlier times. After renewed HTGR interest, we are reporting about the start of new or reactivated coated particle work in several parts of the world, considering the aspects of designs/ traditional and new materials, manufacturing technologies/ quality control quality assurance, irradiation and accident performance, modeling and performance predictions, and fuel cycle aspects and spent fuel treatment. In very general terms, the coated particle should be strong, reliable, retentive, and affordable. These properties have to be quantified and will be eventually optimized for a specific application system. Results obtained so far indicate that the same particle can be used for steam cycle applications with $700-750^{\circ}C$ helium coolant gas exit, for gas turbine applications at $850-900^{\circ}C$ and for process heat/hydrogen generation applications with $950^{\circ}C$ outlet temperatures. There is a clear set of standards for modem high quality fuel in terms of low levels of heavy metal contamination, manufacture-induced particle defects during fuel body and fuel element making, irradiation/accident induced particle failures and limits on fission product release from intact particles. While gas-cooled reactor design is still open-ended with blocks for the prismatic and spherical fuel elements for the pebble-bed design, there is near worldwide agreement on high quality fuel: a $500{\mu}m$ diameter $UO_2$ kernel of 10% enrichment is surrounded by a $100{\mu}m$ thick sacrificial buffer layer to be followed by a dense inner pyrocarbon layer, a high quality silicon carbide layer of $35{\mu}m$ thickness and theoretical density and another outer pyrocarbon layer. Good performance has been demonstrated both under operational and under accident conditions, i.e. to 10% FIMA and maximum $1600^{\circ}C$ afterwards. And it is the wide-ranging demonstration experience that makes this particle superior. Recommendations are made for further work: 1. Generation of data for presently manufactured materials, e.g. SiC strength and strength distribution, PyC creep and shrinkage and many more material data sets. 2. Renewed start of irradiation and accident testing of modem coated particle fuel. 3. Analysis of existing and newly created data with a view to demonstrate satisfactory performance at burnups beyond 10% FIMA and complete fission product retention even in accidents that go beyond $1600^{\circ}C$ for a short period of time. This work should proceed at both national and international level.

논벼재배에 있어서의 노동력 절감에 관한 연구 (A Study on Labor Saving in Paddy Rice Cultivation)

  • 장영철
    • 한국작물학회지
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    • 제11권
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    • pp.81-97
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    • 1972
  • 논벼농사의 노동력을 덜기 위하여 이중 가장 중요한 호미질에 의한 중경제초의 노력을 살초제에 의한 것으로 전환시키고자 기초적인 면과 실제적인 면으로 시험조사를 하였다. 건국대학교에서 1m평방 안높이 21cm 및 36cm의 두 형의 concrete tank를 각 4개씩 만들고 그 안에 채수관장치를 한 뒤 양토작토로 논벼를 심어 수도물로 관수하고 투수속도와 산소침투 정도와 수량과의 관계를 보았다. 농림부 자재 검사소 내에서 투수가 심한 사질답전포장에 전면적으로 살초제 Stam F-34를 살포하여 제초하고 제 1구는 중경을 하지 않고, 제 2구는 중경 1회, 그리고 제 3구는 중경 2회하여 중경의 효과를 비교하였다. 이리 호남시험장내 건답보통논과 습답에 무중경, 중경 1회 중경 2회의 구와 살초제 Pamcon을 살포한 것들 중, 무중경, 중경 1회 제초 2회, 중경 2회 제초 1회, 중경 3회 제초 2회의 구와 그리고 관행구를 설치하여 중경제초의 비용과 살초제에 의한 비용을 비교하였던바 그 결과를 요약하면 다음과 같다. (1) 투수속도와 산소침투와 수량과의 관계는 일당(24시간당) 투수속도 4cm이상 될 때 지표 2cm하에 산소가 조금 들어가며 3cm보다 적을 때는 산소가 지표하의 매우 옅은 층에만 내려가는 것으로 나타나며 그리고 경심 15cm구에는 일당 투수속도의 0cm(무투수) 1.5cm에서 수량이 많고 2.5cm와 3.4cm에는 감수되며, 경심 30cm구에는 투수속도 1.5cm 및 30cm구에서 수량이 많고 무투수와 투수속도 4cm구에는 수량이 떨어졌다. (2) 투수가 심한 농림부 자재검사소 사질토양에서는 중경의 효과가 없었다. (3) 호남작물시험장내 건답에서는 살초제 Pamcon 처리 무중경구 수량에 대해서 유의성이 보이는 증수구는 없었다. 그리고 습답에서는 무중경구에 있어서 중경제초 및 관행구가 유의성 있게 증수되었다. (4) 논매기 호미질에 의한 10a당 노동력은 정미 37.1시간 식사와 휴식시간 포함하여 53.5시간이고, 노임은 2,346원인데 대하여 살초제 사용에의 한제 초노력은 수동식으로 0.5일 즉 약 5시간 제비용과 감수추정량을 추정할 때 1,130원이고 습답을 제외하면 750원이 되는 것으로 추정 되었다.

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