• 제목/요약/키워드: LWR

검색결과 188건 처리시간 0.028초

Oncologic Safety of Laparoscopic Wedge Resection with Gastrotomy for Gastric Gastrointestinal Stromal Tumor: Comparison with Conventional Laparoscopic Wedge Resection

  • Lee, Sejin;Kim, You Na;Son, Taeil;Kim, Hyoung-Il;Cheong, Jae-Ho;Hyung, Woo Jin;Noh, Sung Hoon
    • Journal of Gastric Cancer
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    • 제15권4호
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    • pp.231-237
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    • 2015
  • Purpose: Various laparoscopic wedge resection (LWR) techniques requiring gastrotomy for gastrointestinal stromal tumors (GISTs) of the stomach have been applied to facilitate tumor resection and preserve the remnant gastric volume. However, there is the possibility of cancer cell dissemination during these procedures. The aim of this study was to assess the oncologic safety of LWR with gastrotomy (LWR-G) compared to LWR without luminal exposure. Materials and Methods: Clinicopathologic and operative results of 193 patients who underwent LWR for gastric GIST were retrospectively analyzed from 2003 to 2013. We stratified the patients into two groups: LWR-G and LWR without gastrotomy (LWR-C). Clinicopathologic features, short-term outcomes, and long-term outcomes were compared. Results: A total of 26 patients underwent LWR-G, and 167 patients underwent LWR-C. The LWR-G group showed significantly more anterior wall-located (n=10, 38.5%), intraluminal (n=20, 76.9%), and ulcerative (n=13, 50.0%) tumors than the LWR-C group (n=33, 19.8%; n=96, 57.5%; n=46, 27.5%, respectively). Postoperative short-term outcomes did not differ between the two groups. When tumor staging was compared, no statistical difference was noted. There was no recurrence in the LWR-G group, while 2 patients in the LWR-C group experienced recurrence. The two recurrences in the LWR-C group were found in the liver and in the remnant stomach at 63 and 12 months after the operation, respectively. No gastric GIST-related death was recorded in any group during the study period. Conclusions: LWR-G for gastric GIST is an oncologically safe procedure even for masses with ulcerations.

유전 알고리즘을 이용한 국소가중회귀의 다중모델 결합을 위한 점진적 앙상블 학습 (Incremental Ensemble Learning for The Combination of Multiple Models of Locally Weighted Regression Using Genetic Algorithm)

  • 김상훈;정병희;이건호
    • 정보처리학회논문지:소프트웨어 및 데이터공학
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    • 제7권9호
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    • pp.351-360
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    • 2018
  • 전통적으로 나태한 학습에 해당하는 국소가중회귀(LWR: Locally Weighted Regression)모델은 입력변수인 질의지점에 따라 예측의 해를 얻기 위해 일정구간 범위내의 학습 데이터를 대상으로 질의지점의 거리에 따라 가중값을 달리 부여하여 학습 한 결과로 얻은 짧은 구간내의 회귀식이다. 본 연구는 메모리 기반학습의 형태에 해당하는 LWR을 위한 점진적 앙상블 학습과정을 제안한다. LWR를 위한 본 연구의 점진적 앙상블 학습법은 유전알고리즘을 이용하여 시간에 따라 LWR모델들을 순차적으로 생성하고 통합하는 것이다. 기존의 LWR 한계는 인디케이터 함수와 학습 데이터의 선택에 따라 다중의 LWR모델이 생성될 수 있으며 이 모델에 따라 예측 해의 질도 달라질 수 있다. 하지만 다중의 LWR 모델의 선택이나 결합의 문제 해결을 위한 연구가 수행되지 않았다. 본 연구에서는 인디케이터 함수와 학습 데이터에 따라 초기 LWR 모델을 생성한 후 진화 학습 과정을 반복하여 적절한 인디케이터 함수를 선택하며 또한 다른 학습 데이터에 적용한 LWR 모델의 평가와 개선을 통하여 학습 데이터로 인한 편향을 극복하고자 한다. 모든 구간에 대해 데이터가 발생 되면 점진적으로 LWR모델을 생성하여 보관하는 열심학습(Eager learning)방식을 취하고 있다. 특정 시점에 예측의 해를 얻기 위해 일정구간 내에 신규로 발생된 데이터들을 기반으로 LWR모델을 생성한 후 유전자 알고리즘을 이용하여 구간 내의 기존 LWR모델들과 결합하는 방식이다. 제안하는 학습방법은 기존 단순평균법을 이용한 다중 LWR모델들의 선택방법 보다 적합도 평가에서 우수한 결과를 보여주고 있다. 특정지역의 시간 별 교통량, 고속도로 휴게소의 시간별 매출액 등의 실제 데이터를 적용하여 본 연구의 LWR에 의한 결과들의 연결된 패턴과 다중회귀분석을 이용한 예측결과를 비교하고 있다.

LIGHT WATER REACTOR (LWR) SAFETY

  • Sehgal Bal Raj
    • Nuclear Engineering and Technology
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    • 제38권8호
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    • pp.697-732
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    • 2006
  • In this paper, a historical review of the developments in the safety of LWR power plants is presented. The paper reviews the developments prior to the TMI-2 accident, i.e. the concept of the defense in depth, the design basis, the large LOCA technical controversies and the LWR safety research programs. The TMI-2 accident, which became a turning point in the history of the development of nuclear power is described briefly. The Chernobyl accident, which terrified the world and almost completely curtailed the development of nuclear power is also described briefly. The great international effort of research in the LWR design-base and severe accidents, which was, respectively, conducted prior to and following the TMI-2 and Chernobyl accidents is described next. We conclude that with the knowledge gained and the improvements in plant organisation/management and in the training of the staff at the presently-installed nuclear power stations, the LWR plants have achieved very high standards of safety and performance. The Generation 3+LWR power plants, next to be installed, may claim to have reached the goal of assuring the safety of the public to a very large extent. This review is based on the historical developments in LWR safety that occurred primarily in USA, however, they are valid for the rest of the Western World. This review can not do justice to the many fine contributions that have been made over the last fifty years to the cause of LWR safety. We apologize if we have not mentioned them. We also apologize for not providing references to many of the fine investigations, which have contributed towards LWR safety earning the conclusions that we describe just above.

Monte Carlo analysis of LWR spent fuel transmutation in a fusion-fission hybrid reactor system

  • Sahin, Sumer;Sahin, Haci Mehmet;Tunc, Guven
    • Nuclear Engineering and Technology
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    • 제50권8호
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    • pp.1339-1348
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    • 2018
  • The aim of this paper is to determine neutronic performances of the light water reactor (LWR) spent fuel mixed with fertile thorium fuel in a FFHR. Time dependent three dimensional calculations for major technical data, such as blanket energy multiplication, tritium breeding ratio, cumulative fissile fuel enrichment and burnup have been performed by using Monte Carlo Neutron-Particle Transport code MCNP5 1.4, coupled with a novel interface code MCNPAS, which is developed by our research group. A self-sustaining tritium breeding ratio (TBR>1.05) has been kept throughout the calculations. The study has shown that the fissile fuel quality will be improved in the course of the transmutation of the LWR spent in the FFHR. The latter has gained the reusable fuel enrichment level conventional LWRs between one and two years. Furthermore, LWR spent fuel - thorium mixture provides higher burn-up values than in light water reactors.

MICROSTRUCTURE AND MECHANICAL STRENGTH OF SURFACE ODS TREATED ZIRCALOY-4 SHEET USING LASER BEAM SCANNING

  • Kim, Hyun-Gil;Kim, Il-Hyun;Jung, Yang-Il;Park, Dong-Jun;Park, Jeong-Yong;Koo, Yang-Hyun
    • Nuclear Engineering and Technology
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    • 제46권4호
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    • pp.521-528
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    • 2014
  • The surface modification of engineering materials by laser beam scanning (LBS) allows the improvement of properties in terms of reduced wear, increased corrosion resistance, and better strength. In this study, the laser beam scan method was applied to produce an oxide dispersion strengthened (ODS) structure on a zirconium metal surface. A recrystallized Zircaloy-4 alloy sheet with a thickness of 2 mm, and $Y_2O_3$ particles of $10{\mu}m$ were selected for ODS treatment using LBS. Through the LBS method, the $Y_2O_3$ particles were dispersed in the Zircaloy-4 sheet surface at a thickness of 0.4 mm, which was about 20% when compared to the initial sheet thickness. The mean size of the dispersive particles was 20 nm, and the yield strength of the ODS treated plate at $500^{\circ}C$ was increased more than 65 % when compared to the initial state. This strength increase was caused by dispersive $Y_2O_3$ particles in the matrix and the martensite transformation of Zircaloy-4 matrix by the LBS.

Development of thermal conductivity model with use of a thermal resistance circuit for metallic UO2 microcell nuclear fuel pellets

  • Heung Soo Lee;Dong Seok Kim;Dong-Joo Kim;Jae Ho Yang;Ji-Hae Yoon;Ji Hwan Lee
    • Nuclear Engineering and Technology
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    • 제55권10호
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    • pp.3860-3865
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    • 2023
  • A metallic microcell UO2 pellet has a microstructure where a metal wall is connected to overcome the low thermal conductivity of the UO2 fuel pellet. It has been verified that metallic microcell fuel pellets provide an impressive reduction of the fuel centerline temperature through a Halden irradiation test. However, it is difficult to predict the effective thermal conductivity of these pellets and researchers have had to rely on measurement and use of the finite element method. In this study, we designed a unit microcell model using a thermal resistance circuit to calculate the effective thermal conductivity on the basis of the microstructure characteristics by using the aspect ratio and compared the results with those of reported metallic UO2 microcell pellets. In particular, using the thermal conductivity calculated by our model, the fuel centerline temperature of Cr microcell pellets on the 5th day of the Halden irradiation test was predicted within 6% error from the measured value.