• 제목/요약/키워드: Location Information Assurance

검색결과 13건 처리시간 0.018초

Optimal sensor placement for mode shapes using improved simulated annealing

  • Tong, K.H.;Bakhary, Norhisham;Kueh, A.B.H.;Yassin, A.Y. Mohd
    • Smart Structures and Systems
    • /
    • 제13권3호
    • /
    • pp.389-406
    • /
    • 2014
  • Optimal sensor placement techniques play a significant role in enhancing the quality of modal data during the vibration based health monitoring of civil structures, where many degrees of freedom are available despite a limited number of sensors. The literature has shown a shift in the trends for solving such problems, from expansion or elimination approach to the employment of heuristic algorithms. Although these heuristic algorithms are capable of providing a global optimal solution, their greatest drawback is the requirement of high computational effort. Because a highly efficient optimisation method is crucial for better accuracy and wider use, this paper presents an improved simulated annealing (SA) algorithm to solve the sensor placement problem. The algorithm is developed based on the sensor locations' coordinate system to allow for the searching in additional dimensions and to increase SA's random search performance while minimising the computation efforts. The proposed method is tested on a numerical slab model that consists of two hundred sensor location candidates using three types of objective functions; the determinant of the Fisher information matrix (FIM), modal assurance criterion (MAC), and mean square error (MSE) of mode shapes. Detailed study on the effects of the sensor numbers and cooling factors on the performance of the algorithm are also investigated. The results indicate that the proposed method outperforms conventional SA and Genetic Algorithm (GA) in the search for optimal sensor placement.

APPLICATION OF FUZZY SET THEORY IN SAFEGUARDS

  • Fattah, A.;Nishiwaki, Y.
    • 한국지능시스템학회:학술대회논문집
    • /
    • 한국퍼지및지능시스템학회 1993년도 Fifth International Fuzzy Systems Association World Congress 93
    • /
    • pp.1051-1054
    • /
    • 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.

  • PDF

나선형 토모테라피 방사선치료의 환자별 품질관리를 위한 라디오크로믹 필름 및 Dosimetry CheckTM의 성능평가 (Performance Evaluation of Radiochromic Films and Dosimetry CheckTM for Patient-specific QA in Helical Tomotherapy)

  • 박수연;채문기;임준택;권동열;김학준;정은아;김종식
    • 대한방사선치료학회지
    • /
    • 제32권
    • /
    • pp.93-109
    • /
    • 2020
  • 목 적: 나선형 토모테라피 방사선치료를 위한 환자별 품질관리용 라디오크로믹 필름 및 3차원 분석시스템인 Dosimetry CheckTM (DC, MathResolutions, USA)의 성능평가를 시행하였다. 대상 및 방법: 인체모형팬톰(Anderson Rando Phantom, USA)을 이용하여 위치 변이가 있는 3가지 형태의 복부 종양(130.6㎤), 복막 후면 종양(849.0㎤) 및 전 복부 전이 종양(3131.0㎤)을 모델링하였다. 조사면 고정너비(field width, FW)를 2.5-cm, 5.0-cm, 피치(pitch) 0.287, 0.43으로 하여 부위별 4개씩(plan01-plan04), 총 12개의 비교용 치료계획을 수립하였다. 이온전리함(1D)과 라디오크로믹 필름(Gafchromic EBT3, Ashland Advanced Materials, USA)을 치즈팬톰 내 삽입하는 방법(2D)과 빔 플루언스 로그정보를 이용하여 CT영상 위에 선량을 3차원으로 재구성하는 방식의 DC측정을 진행하였다. 스레드효과(thread effect)를 분석을 위해 리플(ripple) 진폭(%)를 계산하였고, 선량 분포의 패턴 분석을 위해 감마인덱스 분석(DD: 3%/DTA: 3mm, 합격 문턱 값: 95%)을 수행하였다. 결 과: 리플 진폭 측정 결과 복막 후면 종양이 평균 23.1%로 가장 높았다. 라디오크로믹 필름의 분석결과, 절대 선량 평균 1.0±0.9%, 감마인덱스분석 평균 96.4±2.2%로 95% 이상 통과하였으나 전 복부 전이 종양과 같이 넓은 부위 평가에 범위의 제한적이었다. 인체모형팬톰에 적용한 DC 분석결과 FW가 5.0-cm인 세 부위의 2D 및 3D 플랜 평균이 91.8±6.4%였다. 세 단면 및 선량 프로파일 분석을 통해 복막 후면 및 전 복부 종양 표적 전체 영역에 분석이 가능하였고, 선량-용적 히스토그램을 통한 계획 선량 대 측정의 선량 오차가 FW 및 pitch에 따라 커지는 것을 확인하였다. 결 론: DC측정방법은 별도의 측정기 없이 조사 중 측정된 빔 플루언스 로그정보만으로 3차원 환자 영상 데이터 위에 선량 오류를 구현할 수 있고 종양의 위치나 크기에 제한이 없어 크고 불규칙한 종양의 나선형 토모테라피의 치료 시 환자별 품질관리 성능이 매우 우수하며 활용도가 높을 것으로 생각한다.