• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2016.10a
• /
• pp.479-480
• /
• 2016

• Journal of Radiation Protection and Research
• /
• v.37 no.4
• /
• pp.226-230
• /
• 2012

The gross alpha analysis of nasal smear samples for the radiation emergency and the additional follow-up steps were established. Cotton swab sticks using in local hospitals for nasal smear in Korea were used for the verification. The measurement results of standard samples spiked with certified reference source were well agreed within ${\pm}20%$ compared with reference values. The clearance ratio of smear samples conducted with wet smear condition showed higher value. To eliminate the quenching effect of liquid scintillation samples, dry of smear samples should be followed up before counting samples. Based on the measurement results, medical decision levels and internal dose assessment were established for the victims in the beginning of radiation emergency.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.06a
• /
• pp.194-195
• /
• 2005

방사선관리구역 내에서 발생되는 많은 양(발전소별 연간 약$100{\sim}700$개 정도)의 사용 후 공기정화 필터는 고체 폐기물 드럼의 단면적 보다 넓어 별도로 필터를 압축하거나 분해 작업 없이는 폐기물로 직접 처리가 곤란하다. 처리 시 많은 양의 분진이 발생하여 작업자의 내부피폭 가능성 및 많은 양의 고체 폐기물이 발생할 수 있는 잠재성이 있어 시료분석 결과 오염된 필터 내지는 바로 드럼 처리하여 내부 피폭 가능성을 미연에 방지하고 필터 프레임은 재사용을 유도하여 폐기물 저감화, 작업환경 개선 및 경제적인 이익을 창출할 수 있다. 영광 3발전소와 울진 3발전소의 경우 타 발전소에 비해 방사선관리구역 내 공기정화 처리기의 설치수량이 많아(약 700개/년) 공기정화필터가 매년 다수 발생되고 있으며, 이를 전량 드럼 처리 시 고체폐기물 드럼이 더 발생하게 되어 영구처분비용의 증가를 초래하게 된다. 발전소 전체적으로는 약 3,500개/년의 폐필터가 발생되고 있다. 이렇게 발생되는 공기정화필터의 프레임을 재사용함으로써 그 효과는 1) 알루미늄을 포함한 유리섬유를 드럼처리 시 고체방사성 폐기물드럼 생성량 감소 2) 프레임 재사용으로 인한 예산절감 효과 3) 폐필터 분해작업 시 분진에 의한 작업자 체내${\cdot}$외 피폭방지와 작업장 오염 확산 방지 및 환경 개선 4) 작업시간 단축 및 소요인력 감소 효과를 볼 수 있다.

• Journal of Radiation Protection and Research
• /
• v.17 no.2
• /
• pp.15-23
• /
• 1992

Transport behaviors of Cs-137 and Sr-90 were analyzed and ingestion doses were calculated using dynamic model for rice field-rice-man pathway. Cs-137 binding strongly to soil remain longer in rice field than Sr-90. Foliar deposition on rice plant during growing period is the main contamination mechanism.

• 대한방사선방어학회:학술대회논문집
• /
• 2009.11a
• /
• pp.94-95
• /
• 2009

• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.10a
• /
• pp.1147-1148
• /
• 2004

• Proceedings of the Korean Nuclear Society Conference
• /
• 2003.05a
• /
• pp.341.2-341.2
• /
• 2003

• 대한방사선방어학회:학술대회논문집
• /
• 2010.04a
• /
• pp.110-111
• /
• 2010

• Journal of Radiation Protection and Research
• /
• v.8 no.2
• /
• pp.8-14
• /
• 1983

The doses to Korean adult by a single and chronic intake of tritiated water are determined using a three compartment model, which describes the retention of tritium radionuclide in body water and in bound organic form in the body. The results show that the total dose of a single intake, using retention half-time for the three-compartment of 9, 30, and 450 days, is 17.64 mrads ($176.4{\mu}Gy$) per 1mCi/kg ($3.7{\times}10^7Bq/kg$) intake, 97% of which is due to tritium in body water and 3% to bound tritium in tissue. In the chronic intake of 1mCi/day($3.7{\times}10^7Bq/day$) tritiated water, the total dose is 85.5 mrad/day(0.855mGy/day). Furthermore, in this study (MPC) a and (MPC)w values of tritium for Korean man are calculated by using the modified formula originated from ICRP Publication-2. From the results, we found that the (MPC) a, w values of ICRP underestimated approximately 50%, the (MPC)a, w values of Korean man must be elevated as high as approximately 50% than that of ICRP.

• Journal of Radiation Protection and Research
• /
• v.28 no.3
• /
• pp.207-213
• /
• 2003

Carbon-14 is one of the major radionuclides released by CANDU Nuclear Power Plants(NPPs). It is almost always emitted as gas through the stack. From CANDU NPPs about 95% of all carbon-14 is released as carbon dioxide. Carbon-14 is a low energy beta emitter which, therefore, gives only a small skin dose from external radiation. As carbon dioxide Is physiologically rather inert gases for man's metabolism, the inhalation dose is probably less than 1 % of the ingestion dose. But this source of carbon-14, formed in a closed, nor-oxidative environment, was subsequently released into the workplace as an insoluble particulate when these systems were opened lip for re-tubing at CANDU NPPs. As a part of the improvement of dosimetry program at Wolsong Nuclear Power Plants, the carbon-14 metabolism based on references was investigated and studied to setup the internal dosimetry program due to inhalation of carbon-14.