• 제목/요약/키워드: Low dose radiation

검색결과 936건 처리시간 0.028초

Esophageal tolerance to high-dose stereotactic radiosurgery

  • Lee, Bo Mi;Chang, Sei Kyung;Ko, Seung Young;Yoo, Seung Hoon;Shin, Hyun Soo
    • Radiation Oncology Journal
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    • 제31권4호
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    • pp.234-238
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    • 2013
  • Purpose: Esophageal tolerance is needed to guide the safe administration of stereotactic radiosurgery (SRS). We evaluated comprehensive dose-volume parameters of acute esophageal toxicity in patients with spinal metastasis treated with SRS. Materials and Methods: From May 2008 to May 2011, 30 cases in 27 patients with spinal metastasis received single fraction SRS to targets neighboring esophagus. Endpoints evaluated include length (mm), volume (mL), maximal dose (Gy), and series of dose-volume thresholds from the dose-volume histogram (volume of the organ treated beyond a threshold dose). Results: The median time from the start of irradiation to development of esophageal toxicity was 2 weeks (range, 1 to 12 weeks). Six events of grade 1 esophageal toxicity occurred. No grade 2 or higher events were observed. $V_{15}$ of external surface of esophagus was found to predict acute esophageal toxicity revealed by multivariate analysis (odds radio = 1.272, p = 0.047). Conclusion: In patients with spinal metastasis who received SRS for palliation of symptoms, the threshold dose-volume parameter associated with acute esophageal toxicity was found to be $V_{15}$ of external surface of esophagus. Restrict $V_{15}$ to external surface of esophagus as low as possible might be safe and feasible in radiosurgery.

Quantitative Evaluation of Radiation Dose Rates for Depleted Uranium in PRIDE Facility

  • Cho, Il Je;Sim, Jee Hyung;Kim, Yong Soo
    • Journal of Radiation Protection and Research
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    • 제41권4호
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    • pp.378-383
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    • 2016
  • Background: Radiation dose rates in PRIDE facility is evaluated quantitatively for assessing radiation safety of workers because of large amounts of depleted uranium being handled in PRIDE facility. Even if direct radiation from depleted uranium is very low and will not expose a worker to significant amounts of external radiation. Materials and Methods: ORIGEN-ARP code was used for calculating the neutron and gamma source term being generated from depleted uranium (DU), and the MCNP5 code was used for calculating the neutron and gamma fluxes and dose rates. Results and Discussion: The neutron and gamma fluxes and dose rates due to DU on spherical surface of 30 cm radius were calculated with the variation of DU mass and density. In this calculation, an imaginary case in which DU density is zero was added to check the self-shielding effect of DU. In this case, the DU sphere was modeled as a point. In case of DU mixed with molten salt of 50-250 g, the neutron and gamma fluxes were calculated respectively. It was found that the molten salt contents in DU had little effect on the neutron and the gamma fluxes. The neutron and the gamma fluxes, under the respective conditions of 1 and 5 kg mass of DU, and 5 and $19.1g{\cdot}cm^{-3}$ density of DU, were calculated with the molten salt (LiCl+KCl) of 50 g fixed, and compared with the source term. As the results, similar tendency was found in neutron and gamma fluxes with the variation of DU mass and density when compared with source spectra, except their magnitudes. Conclusion: In the case of the DU mass over 5 kg, the dose rate was shown to be higher than the environmental dose rate. From these results, it is concluded that if a worker would do an experiment with DU having over 5 kg of mass, the worker should be careful in order not to be exposed to the radiation.

Impact of 0.35 T Magnetic Field on Dose Calculation for Non-small Cell Lung Cancer Stereotactic Radiotherapy Plans

  • Jaeman Son;Sung Young Lee;Chang Heon Choi;Jong Min Park;Jung-in Kim
    • Journal of Radiation Protection and Research
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    • 제48권3호
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    • pp.117-123
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    • 2023
  • Background: We investigated the impact of 0.35 T magnetic field on dose calculation for non-small cell lung cancer (NSCLC) stereotactic ablative radiotherapy (SABR) in the ViewRay system (ViewRay Inc.), which features a simultaneous use of magnetic resonance imaging (MRI) to guide radiotherapy for an improved targeting of tumors. Materials and Methods: Here, we present a comprehensive analysis of the effects induced by the 0.35 T magnetic field on various characteristics of SABR plans including the plan qualities and dose calculation for the planning target volume, organs at risk, and outer/inner shells. Therefore, two SABR plans were set up, one with a 0.35 T magnetic field applied during radiotherapy and another in the absence of the field. The dosimetric parameters were calculated in both cases, and the plan quality indices were evaluated using a Monte Carlo algorithm based on a treatment planning system. Results and Discussion: Our findings showed no significant impact on dose calculation under the 0.35 T magnetic field for all analyzed parameters. Nonetheless, a significant enhancement in the dose was calculated on the skin surrounding the tumor when the 0.35 T magnetic field was applied during the radiotherapy. This was attributed to the electron return effect, which results from the deviation of the electrons ejected from tissues upon radiation due to Lorentz forces. These returned electrons re-enter the tissues, causing a local dose increase in the calculated dose. Conclusion: The present study highlights the impact of the 0.35 T magnetic field used for MRI in the ViewRay system for NSCLC SABR treatment, especially on the skin surrounding the tumors.

Local radiotherapy for palliation in multiple myeloma patients with symptomatic bone lesions

  • Lee, Jeong Won;Lee, Jeong Eun
    • Radiation Oncology Journal
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    • 제34권1호
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    • pp.59-63
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    • 2016
  • Purpose: To evaluate the clinical outcomes of symptomatic bone lesions in patients with multiple myeloma (MM) who received local radiotherapy (LRT). Materials and Methods: Fifty-one patients with 87 symptomatic bone lesions treated via LRT were analyzed. LRT was delivered at a median total dose of 21 Gy (range, 12 to 40 Gy) in a median of 7 fractions (range, 4 to 20 fractions). The clinical outcomes of LRT and the factors affecting treatment response were assessed. Results: After a median follow-up time of 66.7 weeks, symptom relief was achieved for 85 of 87 lesions (97.7%). The median time to symptom relief was 7 days from the start of LRT (range, 1 to 67 days). The duration of in-field failure-free survival ranged from 1.1 to 450.9 weeks (median, 66.7 weeks). The radiation dose or use of previous and concurrent chemotherapy was not significantly associated with in-field failure for LRT (p = 0.354, 0.758, and 0.758, respectively). Conclusion: Symptomatic bone lesions in patients with MM can be successfully treated with LRT. A higher radiation dose or the use of concurrent chemotherapy may not influence the in-field disease control. A relatively low radiation dose could achieve remission of symptoms in patients with MM.

사고 대응 작업자 피폭선량 평가 (Dose Assessment for Workers in Accidents)

  • 김준혁;윤선홍;차길용;배진형
    • 방사선산업학회지
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    • 제17권3호
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    • pp.265-273
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    • 2023
  • To effectively and safely manage the radiation exposure to nuclear power plant (NPP) workers in accidents, major overseas NPP operators such as the United States, Germany, and France have developed and applied realistic 3D model radiation dose assessment software for workers. Continuous research and development have recently been conducted, such as performing NPP accident management using 3D-VR based on As Low As Reasonably Achievable (ALARA) planning tool. In line with this global trend, it is also required to secure technology to manage radiation exposure of workers in Korea efficiently. Therefore, in this paper, it is described the application method and assessment results of radiation exposure scenarios for workers in response to accidents assessment technology, which is one of the fundamental technologies for constructing a realistic platform to be utilized for radiation exposure prediction, diagnosis, management, and training simulations following accidents. First, the post-accident sampling after the Loss of Coolant Accident(LOCA) was selected as the accident and response scenario, and the assessment area related to this work was established. Subsequently, the structures within the assessment area were modeled using MCNP, and the radiation source of the equipment was inputted. Based on this, the radiation dose distribution in the assessment area was assessed. Afterward, considering the three principles of external radiation protection (time, distance, and shielding) detailed work scenarios were developed by varying the number of workers, the presence or absence of a shield, and the location of the shield. The radiation exposure doses received by workers were compared and analyzed for each scenario, and based on the results, the optimal accident response scenario was derived. The results of this study plan to be utilized as a fundamental technology to ensure the safety of workers through simulations targeting various reactor types and accident response scenarios in the future. Furthermore, it is expected to secure the possibility of developing a data-based ALARA decision support system for predicting radiation exposure dose at NPP sites.

Determination of optimum gamma ray range for radiation mutagenesis and hormesis in quinoa (Chenopodium quinoa Willd.)

  • Park, Chan Young;Song, Seon Hwa;Sin, Jong Mu;Lee, Hyeon Young;Kim, Jin Baek;Shim, Sang In
    • 한국작물학회:학술대회논문집
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    • 한국작물학회 2017년도 9th Asian Crop Science Association conference
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    • pp.240-240
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    • 2017
  • Quinoa (Chenopodium quinoa Willd.) is one of the ancient crops cultivated in the Andes region at an altitude of 3,500-4000m in Chile and Bolivia from 5000 BC. It contains a large amount of protein, minerals and vitamins in comparison with other crops. The cultivation area has been increasing worldwide because of its excellent resistance to various abiotic stress such as salinity, drought and low temperature. ${\gamma}$-Ray radiation of high dose is often used as a tool to induce mutations in plant breeding, but it has a deleterious effect on organisms. However, the radiation may have a positive stimulatory effect of 'hormesis' in the low dose range. This experiment was carried out to investigate the optimum dose range for creating the quinoa genetic resources and to investigate the hormesis effect at low dose on the quinoa. This experiment was performed for 120 days from November, 2016 to February, 2017 in the greenhouse of Gyeongsang National University. ${\gamma}$-Ray radiation was irradiated to seeds at 0 Gy, 50 Gy, 100 Gy, 200 Gy, 300 Gy, 400 Gy, 600 Gy, 800 Gy and 1000 Gy for 8 hours. (50 Gy) using the low level radiation facility ($Co^{60}$) of Cooperative Research Institute of Radiation Research Institute, KAERI. Fifty seeds were placed on each petri dish lined with wet filter paper and germination rate was measured at a time interval of 2 hours for 40 hrs. The length of the root length was measured one week after germination. Each treatment was carried out in 3 replicates. The growth of seedlings were investigated for 10 days after transplanting of 30 day-old seedlings. The plant height, NDVI, SPAD, Fv/Fm, and panicle weight were measured. The germination rate was highest at 50Gy and 0Gy and the rate of seeds treated with 400Gy or higher rate decreased to 25% of the seeds treated with 50Gy. The emergence rate of seedling in pot experiment was higher at the dose of 200 Gy, 300 Gy and 400 Gy than at 0 and 50Gy. However, the rate was lower at strong radiation higher than 600Gy at which $1^{st}$ leaf was not expanded fully and dead due to extreme overgrowth at 44 days after treatment (DAT). The highest value of panicle weight was observed at 50Gy (6.15g) and 100Gy (5.57g). On the other hand, the weight at high irradiated dose of 300Gy and 400Gy was decreased by about 55% compared to low dose (50 Gy). NDVI measurement also showed the highest value at 50 Gy as the growth progressed. SPAD was the highest at 400 Gy and showed positive correlation with irradiation dose except 0 Gy. Fv/Fm was high at 50 Gy up to 30 DAT and no difference between treatments was observed except for 400 Gy from 44 DAT. The plant height was the highest in 50Gy during the growing period and was higher in the order of 50Dy, 100Gy, 0Gy, 200Gy, 300Gy and 400Gy in 88 DAT. In this experiment, the optimal radiation dose for hormesis was 50Gy and 100Gy, and the optimal radiation dose for mutagenesis seems to be 400 Gy.

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Field-in-Field Technique을 이용한 두경부암의 접합부위 선량개선에 관한 고찰 (Field-in-Field Technique to Improve Dose Distribution in the Junction of the Field with Head & Neck Cancer)

  • 김선명;이영철;정덕양;김영범
    • 대한방사선치료학회지
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    • 제21권1호
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    • pp.17-23
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    • 2009
  • 목 적: 두경부암의 치료에 있어 상부 두경부의 양측면조사면과 하경부의 전방조사면의 접합부위에 균등한 선량을 조사하는 것은 매우 중요하다. 접합부위의 선량분포개선을 위하여 하경부 전방조사면의 치료시 Field-in-Field technique을 이용하여 부족선량(under dose)과 초과선량(over dose)으로 인한 선량불균등을 개선하고 일반치료와의 비교를 통하여 두경부암치료에 적용하고자 한다. 대상 및 방법: 상부 두경부의 양측면 조사시 빔의 확산으로 일어나는 입사점과 출사점의 선량차이를 알아보기 위하여 인체모형팬톰을 이용하였다. 인체모형팬톰을 전산화단층촬영하고 전산화치료계획에서 관심점의 선량비교를 시행하였고, 하경부 접합부위의 선량비율을 계산하여 이를 보정하였다. 조사면 접합부위의 선량분포를 알아보기 위하여 하경부의 접합부위에 저감도 필름을 놓고 일반적인 치료인 상부 두경부의 양측면조사와 하경부의 전방조사시 선량분포를 측정하였다. 또한, 상부 두경부 양측면 조사에 따른 빔의 확산을 고려한 Field-in-Field technique을 이용하여 하경부 전방조사를 할 때의 접합부위의 선량분포 차이를 측정하여 비교하였다. 접합부위의 관심점 선량을 알아보기 위하여 열형광선량계를 이용하여 인체모형팬톰내의 관심점에서의 선량변화를 비교, 분석하였다. 결 과: 전산화치료계획에서 하경부의 접합부위에 Field-in-Field technique을 적용하여 치료계획시 상부 두경부 양측면 조사와 선량합성을 한 경우 부족선량 영역의 선량이 4.7~8.65% 이상 증가하였다. 초과선량 영역의 선량도 2.75~10.45% 감소하였다. 또한, 저감도 필름을 이용한 측정에서는 부족선량영역에서 11.3% 증가, 초과선량영역에서 5.3% 감소한 것으로 나타났다. 열형광선량계를 이용한 관심점선량측정에서도 Field-in-Field technique 적용시 부족선량을 최소 7.5%에서 최대 17.6%까지 보정해주는 것으로 나타나 불균등한 선량분포를 개선할 수 있었다. 결 론: 전산화치료계획시 빔의 확산을 고려한 Field-in-Field technique을 적용하면 접합부위의 선량보정을 통해 냉점(cold spot)과 온점(hot spot)을 줄일 수 있었으며 특히, 빔의 확산에 따른 입사점의 부족선량을 보정할 수 있었다. 본 실험을 통해 Field-in-Field technique의 임상적용시 경부임파절의 저선량으로 인한 임파절전이에 대한 위험도를 감소시킬 수 있을 것으로 사료된다.

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토모테라피를 이용한 폐종양 방사선수술 계획 시 선량 분석 (Analysis on the Calculated Dose in the Lung Radiation Surgery Planning Using TomoTherpay)

  • 송주영;정재욱;윤미선;안성자;정웅기;나병식;남택근
    • 한국의학물리학회지:의학물리
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    • 제22권4호
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    • pp.178-183
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    • 2011
  • 본 연구에서는 토모테라피를 이용한 폐종양의 방사선수술 치료계획을 수립한 후 기존의 선형가속기를 사용하였을 경우와 비교, 분석하여 선량분포 측면에서 유효성 및 타당성을 살펴보았다. 종양의 움직임이 5 mm 이하인 10명의 환자 CT 영상을 대상으로 기존의 선형가속기를 이용한 세기조절방사선수술에서와 동일한 처방선량과 동일한 조건의 중요장기 선량제한치로 토모테라피 치료계획을 수립한 후 선량분포를 비교하였다. 토모테라피를 이용한 결과에서도 기존의 선형가속기를 이용한 세기조절방사선수술과 동일하게 중요장기의 선량제한치를 충족시키면서 GTV에 처방선량을 부여할 수있음을 확인하였다. 방사선조사로 인한 폐의 정상조직합병증확률과 종양 반대편 폐의 등가균일선량 측면에서는 토모테라피가 기존 선형가속기보다 상대적으로 더 우수한 결과를 보였으나, 종양 내 치료선량 분포의 균일도에서는 기존 선형 가속기가 더 양호한 결과를 보였다. 치료 빔 전달 시간측면에서는 토모테라피가 기존 선형가속기 경우보다 2배 이상의 시간이 소요되었다. 이와 같은 본 연구의 결과 분석을 통해 폐종양 부위의 움직임이 적은 경우, 환자의 상태와 선량분포의 적합성 등을 고려한 최적의 치료계획을 세운다면 토모테라피를 사용하는 방사선 수술이 유효성 및 타당성이 있음을 확인할 수 있었다.

DEVELOPMENT OF THE DUAL COUNTING AND INTERNAL DOSE ASSESSMENT METHOD FOR CARBON-14 AT NUCLEAR POWER PLANTS

  • Kim, Hee-Geun;Kong, Tae-Young;Han, Sang-Jun;Lee, Goung-Jin
    • Journal of Radiation Protection and Research
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    • 제34권2호
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    • pp.55-64
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    • 2009
  • In a pressurized heavy water reactor (PHWR), radiation workers who have access to radiation controlled areas submit their urine samples to health physicists periodically; internal radiation exposure is evaluated by the monitoring of these urine samples. Internal radiation exposure at PHWRs accounts for approximately 20 $\sim$ 40% of total radiation exposure; most internal radiation exposure is attributed to tritium. Carbon-14 is not a dominant nuclide in the radiation exposure of workers, but it is one potential nuclide to be necessarily monitored. Carbon-14 is a low energy beta emitter and passes relatively easily into the body of workers by inhalation because its dominant chemical form is radioactive carbon dioxide ($^{14}CO_2$). Most inhaled carbon-14 is rapidly exhaled from the worker's body, but a small amount of carbon-14 remains inside the body and is excreted by urine. In this study, a method for dual analysis of tritium and carbon-14 in urine samples of workers at nuclear power plants is developed and a method for internal dose assessment using its excretion rate result is established. As a result of the developed dual analysis of tritium and carbon-14 in urine samples of radiation workers who entered the high radiation field area at a PHWR, it was found that internal exposure to carbon-14 is unlikely to occur. In addition, through the urine counting results of radiation workers who participated in the open process of steam generators, it was found that the likelihood of internal exposure to either tritium or carbon-14 is extremely low at pressurized water reactors (PWRs).

일 지역 종합병원 영상의학과 MDCT선량에 대한 연구 (The study of MDCT of Radiation dose in the department of Radiology of general hospitals in the local area)

  • 신정섭
    • 한국방사선학회논문지
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    • 제6권4호
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    • pp.281-290
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    • 2012
  • 경상북도에 소재한 3개 종합병원 영상의학과의 MDCT 검사 중 두부, 복부, 흉부 각 10건씩 30건을 대상으로 CTDIl, DLP, Slice 수, DLP/Slice 수를 조사하여 병원 간 프로토콜의 차이로 인한 MDCT의 피폭선량의 차이를 분석하였고, CT검사의 가장 많은 검사건수를 차지하고 프로토콜이 비교적 단순한 두부 CT를 Helical Scan과 Normal Scan으로 2회 실시하여 영상의 화질, CTDI, DLP, 안구의 피폭선량, 갑상선의 피폭선량의 차이를 분석하였다. 두부CT에서 조사대상 병원의 3분의 2에서 CTDI 참조준위(IAEA 50mGy, 우리나라 60mGy)를 초과하지 않은 A병원에 비하여 유의하게 높았다(p<0.001). DLP에서 조사병원의 3분의 1은 참조준위 IAEA 1,050mGy.cm, 우리나라 1,000mGy.cm의 권고량 보다 높았고, 3분의 2가 우리나라의 권고량을 초과하고 있었다. 참조준위를 초과하지 않은 A병원에 비하여 유의하게 높았다(p<0.001). Abdomen CT에서도 3분의 1은 CTDI 참조준위 IAEA 25mGy, 우리나라 20mGy보다 높은 119mGy를 보였고, DLP에서는 모든 조사대상 병원이 우리나라 권고량 700mGy.cm보다 높았다. 조사대상 병원 중 모든 검사에서 높은 선량을 보인 C병원은 MPR, 3D 검사의 비중이 높아 낮은 pitch, 높은 관전류 검사로 인한 피폭선량이 높았다. Scan 방법에 따른 피폭선량의 차이를 분석하고자 동일환자의 두부CT를 Normal scan과 Helical scan으로 각각 실시하여 분석한 결과 CTDI 및 DLP에서 Helical CT가 Normal scan에 비해 63.4%, 93.7% 높은 선량을 보였다(p<0.05, p<0.01). 그러나 갑상선의 피폭선량은 Normal scan이 87.26% 높았다(p<0.01). Helical CT의 선속은 종심부와 변연부의 모양이 종의 형태를 취하고 있어 두부CT에서 갑상선은 중심선속에서 벗어난 적은 선량으로 피폭된다. 또한 Helical scan시 Gantry 각을 수직으로 사용하였고, Normal scan시에는 Orbitomeatal line에 평행으로 정렬된 Gantry 각을 사용하여 Helical scan에서 갑상선은 피폭선량이 감소하였다. 그러나 본 연구에서 사용된 프로토콜은 식약청의 표준준위에 비해 높은 피폭선량을 보여 식약청의 권고량을 지키기 위해서는 낮은 관전류 높은 Pitch의 사용이 요구되었다. 이번 연구에서 Normal scan과 Helical scan에 따른 화질의 차이는 없는 것으로 분석되어 특별한 경우가 아니면 Normal scan의 표준화된 프로토콜을 사용하고 갑상선의 보호장구를 사용하는 것이 필요하였다. 이번 연구는 일지역의 CT검사 중 일부를 조사하여 분석하였으므로 CT검사의 전체를 평가하는데 무리가 있었다. 그러나 경우에 따라 환자피폭선량의 가이드 권고량을 초과하고 있음을 알 수 있었고, 병원 간의 피폭선량 편차도 있음을 확인 할 수 있었다. 이것을 개선하기 위하여 영상의학과 의사 및 방사선사는 CT 방사선량을 줄이는 최적화된 프로토콜로 CT검사를 시행해야 하고, 환자의 알권리를 위하여 피폭선량은 공개되어야 한다. 그러나 아직 많은 의사들과 방사선사는 이에 대한 인식이 부족하므로 개선을 위하여 CT선량 저감화의 교육프로그램, CT검사에 따른 피폭선량의 공개, 병원의 서비스평가 및 병원인증제 평가항목에 CT검사 피폭선량관리 및 공개항목을 추가 등의 관련기관의 노력과 의료종사자가 CT검사에서 행위의 최적화를 실현하는 최선의 프로토콜을 사용하는 노력이 필요하였다.