• Title/Summary/Keyword: MIRD-V

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Modification of Trunk Thickness of MIRD phantom Based on the Comparison of Organ Doses with Voxel Phantom (체적소팬텀과의 장기선량 비교를 통한 MIRD팬텀 몸통두께 수정)

  • Lee, Choon-Sik;Park, Sang-Hyun;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.28 no.3
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    • pp.199-206
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    • 2003
  • Because the MIRD phantom, the representative mathematical phantom was developed for the calculation of internal radiation dose, and simulated by the simplified mathematical equations for rapid computation, the appropriateness of application to external dose calculation and the closeness to real human body should be justified. This study was intended to modify the MIRD phantom according to the comparison of the organ absorbed doses in the two phantoms exposed to monoenergetic broad parallel photon beams of the energy between 0.05 MeV and 10 MeV. The organ absorbed doses of the MIRD phantom and the Zubal yokel phantom were calculated for AP and PA geometries by MCNP4C, general-purpose Monte Carlo code. The MIRD phantom received higher doses than the Zubal phantom for both AP and PA geometries. Effective dose in PA geometry for 0.05 MeV photon beams showed the difference up to 50%. Anatomical axial views of the two phantoms revealed the thinner trunk thickness of the MIRD phantom than that of the Zubal phantom. To find out the optimal thickness of trunk, the difference of effective doses for 0.5 MeV photon beams for various trunk thickness of the MIRD phantom from 20 cm to 36 cm were compared. The optimal thunk thickness, 24 cm and 28 cm for AP and PA geometries, respectively, showed the minimum difference of effective doses between the two phantoms. The trunk model of the MIRD phantom was modified and the organ doses were recalculated using the modified MIRD phantom. The differences of effective dose for AP and PA geometries reduced to 7.3% and the overestimation of organ doses decreased, too. Because MIRD-type phantoms are easier to be adopted in Monte Carlo calculations and to standardize, the modifications of the MIRD phantom allow us to hold the advantage of MIRD-type phantoms over a voxel phantom and alleviate the anatomical difference and consequent disagreement in dose calculation.

Calculation of Dose Conversion Coefficients in the Anthropomorphic MIRD Phantom in Broad Unidirectional Beams of Monoenergetic Photons (MIRD 인형팬텀의 넓고 평행한 감마선빔에 대한 선량 환산계수 계산)

  • Chang, Jai-Kwon;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.22 no.1
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    • pp.47-58
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    • 1997
  • The conversion coefficients of effective dose per unit air kerma and equivalent dose per unit fluence were calculated by MCNP4A code for antero-posterior(AP) and postero- anterior(PA) incidence of broad, unidirectional beams of photons into anthropomorphic MIRD phantom. Calculations have been performed for 20 monoenergetic photons of energy ranging from 0.03 to 10 MeV. The conversion coefficients showed a good agreement with the corresponding values given in the draft publication of joint task group of ICRP and ICRU within 10%. The deviations may arise from the differences of geometry in the MIRD phantom and the ADAM/EVE phantoms, and the differences in the codes and cross-section data used. Inclusion of a specific oesophagus model results in effective dose slightly different(5% at most) from the effective doses obtained by adopting the equivalent doses for the thymus or pancreas. Deletion of the ULI from the remainder organ appeared not to be significant for the cases of photon dosimetry covered in this study.

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Construction of MIRD-type Korean Adult Male Phantom and Calculation of Dose Conversion Coefficients for Photon (한국 성인남성 MIRD형 모의피폭체 제작 및 광자 외부피폭 선량환산인자 산출)

  • Park, Sang-Hyun;Lee, Choon-Sik;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.29 no.2
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    • pp.97-104
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    • 2004
  • MIRD-type Korean adult male phantom, 'KMIRD' was constructed to calculate Korean-specific dosimetric quantities for radiation protection consideration. The external shape of KMIRD was based on national physical standard data of Korean. KMIRD has thicket trunk than MIRD5 and arm models divided from trunk. The height and weight of the KMIRD are 171 cm and 63.8 kg. ICRP23 data were referred to constitute organs and tissues of KMIRD. However nine organs were constructed based on Korean reference data provided by Radiation Health Research Institute. In the present study, the MCNPX2.3 Monte Carlo transport code was combined with KMIRD to calculate dose conversion coefficients for photon in the energy range from 0.05 to 10 MeV. The simulated irradiation geometries are broad parallel photon beams in AP, PA, LLAT and RLAT direction. Absorbed dose conversion coefficients were compared with data calculated with MIRD5, MIRD-type phantom based on ICRP23 reference man. In some organs, the discrepancies between two phantoms amount up to nearly 30%. The effective doses conversion coefficients of KMIRD are lower than those of MIRD5. The dose discrepancies between two MIRD-type phantoms ate because of physical differences between Korean and Western, also geometric differences between two phantoms. KMIRD should be revised using the full set of Korean reference data of all organs. The developed MIRD-type Korean adult male phantom can be applied to dose assessment of internal exposure.

Construction of voxel head phantom and application to BNCT dose calculation (Voxel 머리팬텀 제작 및 붕소중성자포획요법 선량계산에의 응용)

  • Lee, Choon-Sik;Lee, Choon-Ik;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.26 no.2
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    • pp.93-99
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    • 2001
  • Voxel head phantom for overcoming the limitation of mathematical phantom in depleting anatomical details was constructed and example dose calculation for BNCT was performed. The repeated structure algorithm of the general purpose Monte Carlo code, MCNP4B was applied for yokel Monte Carlo calculation. Simple binary yokel phantom and combinatorial geometry phantom composed of two materials were constructed for validating the voxel Monte Carlo calculation system. The tomographic images of VHP man provided by NLM(National Library of Medicine) were segmented and indexed to construct yokel head phantom. Comparison of doses for broad parallel gamma and neutron beams in AP and PA directions showed decrease of brain dose due to the attenuation of neutron in eye balls in case of yokel head phantom. The spherical tumor volume with diameter, 5cm was defined in the center of brain for BNCT dose calculation in which accurate 3 dimensional dose calculation is essential. As a result of BNCT dose calculation for downward neutron beam of 10keV and 40keV, the tumor dose is about doubled when boron concentration ratio between the tumor to the normal tissue is $30{\mu}g/g$ to $3{\mu}g/g$. This study established the voxel Monte Carlo calculation system and suggested the feasibility of precise dose calculation in therapeutic radiology.

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Radiation Absorbed Dose Calculation Using Planar Images after Ho-166-CHICO Therapy (Ho-166-CHICO 치료 후 평면 영상을 이용한 방사선 흡수선량의 계산)

  • 조철우;박찬희;원재환;왕희정;김영미;박경배;이병기
    • Progress in Medical Physics
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    • v.9 no.3
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    • pp.155-162
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    • 1998
  • Ho-l66 was produced by neutron reaction in a reactor at the Korea Atomic Energy Institute (Taejon, Korea). Ho-l66 emits a high energy beta particles with a maximum energy of 1.85 MeV and small proportion of gamma rays (80 keV). Therefore, the radiation absorbed dose estimation could be based on the in-vivo quantification of the activity in tumors from the gamma camera images. Approximately 1 mCi of Ho-l66 in solution was mixed into the flood phantom and planar scintigraphic images were acquired with and without patient interposed between the phantom and scintillation camera. Transmission factor over an area of interest was calculated from the ratio of counts in selected regions of the two images described above. A dual-head gamma camera(Multispect2, Siemens, Hoffman Estates, IL, USA) equipped with medium energy collimators was utilized for imaging(80 keV${\pm}$10%). Fifty-nine year old female patient with hepatoma was enrolled into the therapeutic protocol after the informed consent obtained. Thirty millicuries(110MBq) of Ho-166-CHICO was injected into the right hepatic arterial branch supplying hepatoma. When the injection was completed, anterior and posterior scintigraphic views of the chest and pelvic regions were obtained for 3 successive days. Regions of interest (ROIs) were drawn over the organs in both the anterior and posterior views. The activity in those ROIs was estimated from geometric mean, calibration factor and transmission factors. Absorbed dose was calculated using the Marinelli formula and Medical Internal Radiation Dose (MIRD) schema. Tumor dose of the patient treated with 1110 MBq(30 mCi) Ho-l66 was calculated to be 179.7 Gy. Dose distribution to normal liver, spleen, lung and bone was 9.1, 10.3, 3.9, 5.0 % of the tumor dose respectively. In conclusion, tumor dose and absorbed dose to surrounding structures were calculated by daily external imaging after the Ho-l66 therapy for hepatoma. In order to limit the thresholding dose to each surrounding organ, absorbed dose calculation provides useful information.

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Analysis of a Lead Vest Dose Reduction Effect for the Radiation Field at Major Working Places during Refueling Outage of Korean PWR Nuclear Power Plants (국내 가압경수로형 원전 계획예방정비기간 주요 방사선작업에 대한 납 차폐복 선량저감효과 분석)

  • Kim, Jeong-In;Lee, Byoung-Il;Lim, Young-Khi
    • Journal of Radiation Protection and Research
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    • v.38 no.4
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    • pp.237-241
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    • 2013
  • The gamma energy distributions at the major working places during refueling outage of Korean PWR nuclear power plants were measured. In order to estimate the dose reduction effect of a lead vest, Monte Carlo calculation method was used. For the simulations, the MIRD-V phantom with a lead vest was formed and exposed to the measured radiation field. The average measured gamma energy is lower than that of standard which is generally applied to radiation protection procedures. For the efficient use of a lead vest and achievement of radiation protection purpose, it is necessary to estimate the energy distribution of radiation field at working places.

Hospice and Palliative Care for the Terminal Patients with Colorectal Cancer (말기 대장직장암 환자의 호스피스 완화의료)

  • Hong, Young-Hwa;Lee, Choon-Sub;Lee, Ju-Ri;Lee, Jung-Ho;Kim, You-Jin;Lee, Tae-Kgyu;Moon, Do-Ho
    • Journal of Hospice and Palliative Care
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    • v.10 no.1
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    • pp.35-42
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    • 2007
  • Purpose: Colorectal ranter is the 4th leading cause of cancer death in Korea and the prevalence is increasing continuously. This study was aimed to figure out the problems through the clinical consideration about terminal colorectal ranter patients who had died in hospice unit. Methods: We retrospectively reviewed the medical records in 78 patients with colorectal ranter who had admitted, received palliative care, and died in a hospice unit between April 2003 and November 2006. Results: The median age of patients was 59.6 years with 45 men (58%) and 24 women (42%). The median survival in hospice and palliative care was 36 days. The median hospitalization was 22 days. The most prevalent reason for admission was pain (38 patients, 49%), and the most common symptom was also pain (70 patients, 90%). Forty eight patients (62%) took analgesics before hospice referral. Twenty seven patients (65%) of 45 patients with intestinal obstruction have been performed palliative procedures. Median survival of patients with palliative procedure was higher than that of no palliative procedure group (47 days vs 19 days, P-value=0.005). Conclusion: The duration of hospice and palliative care was not enough to care the terminal colorectal cancer. Therefore, we suggest that proper education and information should be provided to physician, patients and their family members for effective hospice and palliative care.

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