• Title/Summary/Keyword: 여성선원

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여성해기사 직업에 관한 인식 조사

  • Jo, So-Hyeon
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • 2013.06a
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    • pp.242-244
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    • 2013
  • 한국에서 해운산업으로 배출되는 여성 인력은 년 간 800여명에 이른다. 그 중 과반수의 이하의 여성인력만이 매 년 해운선사에 취업하여 종사하고 있으나, 여러 가지 현안 사항들로 채용의 기회는 남성에 비해 현재까지는 적은 편이다. 여성 해기사의 고용기피 이유들 중 하나는 여성해기사가 실제 취업활동시 '남성에 비해 우월하지 않을 것이다' 라는 사회적 인식의 차이도 영향을 미친다는 가정하에 실제 여성 해기사와 승선 경험이 있는 선원과 그렇지 않은 선원을 대상으로 여성 해기사의 업무 성취도, 팀협력, 의사소통 능력, 직업 만족도 및 직업에 관한 책임감의 범위로 인식의 차이를 설문조사하였다.

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해운기업 ESG 경영에 대한 연구; 여성 선원 인권을 중심으로

  • 허성례
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • 2023.11a
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    • pp.208-210
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    • 2023
  • 여성해사인의 직업 관련 인식 조사 및 다각화를 위해 M해양대학교 해사대학에 재학 중인 여학생의 승선 및 진로에 대한 설문조사를 실시하였다. 설문 결과를 분석하여 여성해사인의 진로 및 취업에 대한 인식을 파악하고 이를 토대로 학부 교육과정, 학교 취업 프로그램, 학교 생활 규정 분야에서 진로 다각화를 위한 방안 및 시사점을 제언하였다.

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여성해기사의 해상진출을 위한 국제기구의 역량강화 연구

  • Jo, So-Hyeon
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • 2013.06a
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    • pp.457-458
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    • 2013
  • 전 세계 1내지 2 퍼센트에 해당하는 여성선원 중 상선에 종사하는 여성해기사는 그 중 6 퍼센트에 해당한다. 해운 산업의 구성 인력 중 소수라고 할 수 있으나 여성의 원활한 해상 진출을 위해 국제해사기구를 비롯하여 정부, 교육단체, 노조 및 해운선사들의 지원과 관심이 필요한 시점이다. 이에 그 동안 국제해사기구를 비롯하여 여성해기사를 위한 현존 지원 정책을 살펴 보고, 향후 여성해기사의 역량강화 및 해상진출을 위한 제도적, 정책적 요소들을 식별하였다.

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Assessment of Dose Distribution using the MIRD Phantom at Uterine Cervix and Surrounding Organs in High Doserate Brachytheraphy (자궁주위 방사선 근접치료시 MIRD 팬텀을 이용한 주변장기의 피폭환경평가)

  • Lee, Yun-Jong;Nho, Young-Chang;Lee, Jai-Ki
    • Korean Journal of Environmental Biology
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    • v.24 no.4
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    • pp.387-391
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    • 2006
  • Computational and experimental dosimetry of Henschke applicator with respect to high dose rate brachytherapy using the MIRD phantom and a remote control afterloader were performed. A comparison of computational dosimetry was made between the simulated Monte Carlo dosimetry and GAMMADOT brachytherapy Planning system's dosimetry. Dose measurements was performed using ion chamber in a water phantom. Dose rates are calculated using Monte Carlo code MCNP4B and the GAMMADOT. Thecomputational models include the detailed geometry of Ir-192 source, tandem tube, and shielded ovoids for accurate estimation. And transit dose delivered during source extension to and retraction from a given dwell position was estimated by Monte Carlo simulations. Point doses at ICRU bladder/rectal pointswhich have been recommened by ICRU 38 was assessed. Calculated and measured dose distribution data agreed within 4% each other. The shielding effect of ovoids leads to 19% and 20% dose reduction at bladder surface and rectal points.

Assessment of Radiation Dose for Surrounding Organs and Persons Approaching Patients upon Brachytherapy of Cervical Cancer with $^{192}Ir$ ($^{192}Ir$를 사용한 자궁경부암 치료시 주변 장기 및 근접한 사람의 선량 평가)

  • Kang, Se-Sik
    • Journal of radiological science and technology
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    • v.33 no.3
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    • pp.283-288
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    • 2010
  • In order to evaluate radiation dose on the uterus and surrounding organs during brachytherapy for cervical cancer, of which the frequency of occurrence is high in Korean women, as well as radiation dose on medical staffs in proximity of patients receiving the therapy, a mathematical phantom based on reference Korean was established and the radiation dose was calculated accordingly. For simulation, $^{192}Ir$, which is useful in brachytherapy, was selected as radionuclide. Also, it was presumed that the intensity of initial radiation was 1 Ci. The result indicated the radiation of 4.92E-14 Gy/Ci in the uterus, the source organ. In addition, radiation on people around patient receiving the therapy was found to be 1.24E-07 Sv at a distance of 30 cm.

Development of Reference Korean Organ and Effective Dose Calculation Online System (웹 기반 표준한국인 장기 흡수선량 및 유효선량 평가 시스템 개발)

  • Park, Sooyeun;Yeom, Yeon Soo;Kim, Jae Hyeon;Lee, Hyun Su;Han, Min Cheol;Jeong, Jong Hwi;Kim, Chan Hyeong
    • Journal of Radiation Protection and Research
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    • v.39 no.1
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    • pp.30-37
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    • 2014
  • Recently High-Definition Reference Korean-Man (HDRK-Man) and High-Definition Reference Korean-Woman (HDRK-Woman) were constructed in Korea. The HDRK phantoms were designed to represent respectively reference Korean male and female to calculate effective doses for Korean by performing Monte Carlo dose calculation. However, the Monte Carlo dose calculation requires detailed knowledge on computational human phantoms and Monte Carlo simulation technique which regular researchers in radiation protection dosimetry and practicing health physicists do not have. Recently the UFPE (Federal University of Pernambuco) research group has developed, and opened to public, an online Monte Carlo dose calculation system called CALDOSE_X(www.caldose.org). By using the CALDOSE_X, one can easily perform Monte Carlo dose calculations. However, the CALDOSE_X used caucasian phantoms to calculate organ doses or effective doses which are limited for Korean. The present study developed an online reference Korean dose calculation system which can be used to calculate effective doses for Korean.

Effective Doses in the Radial Gamma Radiation Field near a Point Source: Gender Difference and Deviation from the Personal Dose Equivalent (점선원 감마선장에서 유효선량의 성별차 및 개연선량당량과의 차이)

  • Chang, Jai-Kwon;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.22 no.4
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    • pp.299-307
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    • 1997
  • The individual dose equivalent, $H_p$, effective dose, E, and gender specific effective dose, $E^m$ and E$^f$, were evaluated using the male and female phantoms of MIRD type located in the radial gamma radiation field near a point source. The point sources were placed at the distances of 15, 40 and 100 cm in front of the body at different heights. Two radionuclides, $^{137}Cs$ and $^{131}I$, were selected for the illustrative examples. In terms of the gender specific effective doses, $E^f$ is higher than $E^m$ with a few exceptions, e.g. the case where the point source is at the height of reproductive organs, but the differences from the sex- averaged values are not significant enough to justify use of gender specific dose conversion factors for the radial gamma field. The ratios $H_p$/E were in the range of 1 to 3 depending on the source and dosimeter positions when the dosimeter is worn on the front surface of the torso covering from chest to lower abdomen, but varied from 0.34 to 6.5 in extreme cases. When it is assumed that the typical handling procedure of radioactive source material and the typical dosimeter position(on the chest) be respected, the dosimeters calibrated against the broad parallel field appear to provide estimates with acceptable errors for the effective dose of workers exposed to radial broad gamma field around a point source.

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Assessment of Effective Doses in the Radiation Field of Contaminated Ground Surface by Monte Carlo Simulation (몬테칼로 시뮬레이션에 의한 지표면 오염 방사선장에서의 유효선량 평가)

  • Chang, Jai-Kwon;Lee, Jai-Ki;Chang, Si-Young
    • Journal of Radiation Protection and Research
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    • v.24 no.4
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    • pp.205-213
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    • 1999
  • Effective dose conversion coefficients from unit activity radionuclides contaminated on the ground surface were calculated by using MCNP4A rode and male/female anthropomorphic phantoms. The simulation calculations were made for 19 energy points in the range of 40 keV to 10 MeV. The effective doses E resulting from unit source intensity for different energy were compared to the effective dose equivalent $H_E$ of previous studies. Our E values are lower by 30% at low energy than the $H_E$ values given in the Federal Guidance Report of USEPA. The effective dose response functions derived by polynomial fitting of the energy-effective dose relationship are as follows: $f({\varepsilon})[fSv\;m^2]=\;0.0634\;+\;0.727{\varepsilon}-0.0520{\varepsilon}^2+0.00247{\varepsilon}^3,\;where\;{\varepsilon}$ is the gamma energy in MeV. Using the response function and the radionuclide decay data given in ICRP 38, the effective dose conversion coefficients for unit activity contamination on the ground surface were calculated with addition of the skin dose contribution of beta particles determined by use of the DOSEFACTOR code. The conversion coefficients for 90 important radionuclides were evaluated and tabulated. Comparison with the existing data showed that a significant underestimates could be resulted when the old conversion coefficients were used, especially for the nuclides emitting low energy photons or high energy beta particles.

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