• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.15 no.3
• /
• pp.281-299
• /
• 2017

The inventory management of radionuclides is essential for the safe management of disposal facilities. In this study, we compared the activity of dry active waste predicted using the generated waste data and that measured for the accepted waste in the disposal facility. For very low level waste, the measured activity was higher than the predicted activity for $^{137}CS$, $^{90}Sr$, $^{99}Tc$ and $^{129}I$. In low level waste, the predicted activity was higher than the measured activity for all radionuclides. We also evaluated the variation in the predicted quantity and total activity of each level of dry active waste through a sensitivity analysis on a scaling factor. This result will contribute to the construction of a Safety Case and safe operation of disposal facilities.

• Nuclear Engineering and Technology
• /
• v.27 no.2
• /
• pp.260-268
• /
• 1995

국내 원자력발전소의 방사성폐기물 발생량은 초고압 압축, 농축폐액 건조, 페수지 건조 등의 폐기물감용을 위한 운영계획이 수립되고 또한 일부 원자력발전소에서는 1995년부터 운영이 시작될 예정이어서 감소가 예상되고 있다. 원자력발전소로부터 방사성폐기물의 누적량은 2035년까지 운영자의 폐기물 감용 계획을 고려한다면 141,920 드럼으로 예상할 수 있고, 이에 상응하는 방사능량은 반감기가 한달 이상인 30개 핵종에 대하여 방사성 붕괴를 무시할 때 49,390 Ci였다. 특히 원자력환경관리센터에서 수행한 개념설계에 따른 1차 건설예정의 지하 처분동굴의 적재량인 약 10만 드럼은 2014년까지 누적량으로 채울 수 있고 이때 처분장의 장기적 성능평가에 주요 고려 대상인 반감기가 5년 이상의 14개 핵종에 대한누적 방사능량은 약 13,577 Ci였다. 이 예측된 발생량과 재고량은 처분장 장기적 성능 및 안전성 평가에 중요한 기초자료가 될 것이다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.15 no.1
• /
• pp.65-82
• /
• 2017

The result of a preliminary safety assessment that was completed by applying the radionuclide inventory calculated on the basis of available data from radioactive waste generation agencies suggested that many difficulties are to be expected with regard to disposal safety and operation. Based on the results of the preliminary safety assessment of the entire disposal system, in this paper, a unit package exceeding the safety goal is selected that occupies a large proportion of radionuclides in intermediate-level radioactive waste. We introduce restrictions on the amount of radioactivity in a way that excludes the high surface dose rate of the package. The radioactivity limit for disposal will be used as the baseline data for establishing the acceptance criteria and the disposal criteria for each disposal facility to meet the safety standards. It is necessary to draw up a comprehensive safety development plan for the Gyeongju waste disposal facility that will contribute to the construction of a Safety Case for the safety optimization of radioactive waste disposal facilities.

• 대한방사선방어학회:학술대회논문집
• /
• 2011.11a
• /
• pp.326-327
• /
• 2011

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.15 no.3
• /
• pp.265-279
• /
• 2017

The Gyeongju underground silo type disposal facility, approved for use in December 2014, is in operation for the disposal of low and very low-level radioactive wastes, excluding intermediate-level waste. That is why the existing low-level radioactive waste level has been subdivided and the concentration limit value for intermediate-level waste has been changed in accordance with Nuclear Safety Commission Notice 2014-003. For the safe disposal of intermediate-level wastes, new optimization methodology for calculating the concentration limit of intermediate radioactive level wastes at an underground silo type disposal facility was developed. According to the developed optimization methodology, concentration limits of intermediate-level wastes were derived and the inventory of radioactive nuclides was evaluated. The operation and post closure scenarios were evaluated for the derived radioactive nuclide inventory and the results of all scenarios were confirmed to meet the regulatory limit. However, in case of $^{14}C$, it was confirmed that additional radioactivity limitation through a well scenario was needed in addition to the limit of disposal concentration. It was confirmed that the derived intermediate concentration limit of radioactive waste can be used as the intermediate-level waste concentration limit for the underground disposal facility. For the safe disposal of intermediate-level wastes, KORAD plans to acquire additional data from the radioactive waste generator and manage the cumulative radioactivity of $^{14}C$.

• Nuclear industry
• /
• v.16 no.2 s.156
• /
• pp.16-21
• /
• 1996

지난해 우리나라 총 전력생산량 중 36$\%$를 원자력발전이 담당하였고, 그만큼 전력생산에서 차지하는 원전의 비중이 커서, 그 중요성은 어느 때보다도 부각되고 있다. 현재 우리나라의 전력수요는 매년 10$\%$ 이상 급격히 증가하고 있고, 또 자원이 없는 우리나라로서는 원자력발전을 계속 추구할 수 밖에 없다. 그러나 원전에는 원료로 우라늄을 사용하고 있기 때문에 이 우라늄의 연소과정에서 방사성물질이 발생되고 또 이 중 일부가 방사성폐기물로 외부환경에 방출된다. 원전에서는 이런 폐기물 방출을 억제할 수 있는 시설이 충분히 갖추어져 있어 방출량이 극소량이 되도록 하고 있지만, 이런 소량 방출에도 원전 주변환경이 과연 안전하게 보전되었는지 지난해 수행한 환경방사능 조사결과를 요약$\cdot$정리하면서 알아본다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05b
• /
• pp.651-658
• /
• 1998

최근 원자력발전소주변 환경방사선에 대한 국민적 관심이 고조되고 있으나 환경중 방사능 축적에 대한 허용기준치가 정립되어 있지 않아 효과적인 대 국민 홍보에 한계가 있다. 따라서 원전 주변 주민의 생활습관을 파악하여 섭취량을 품종별로 분류하여, 조사, 분석함으로서 환경시료중 방사능 허용농도를 설정함으로서 원자력발전소 주변 환경방사능 농도를 설정된 허용농도와 비교하여 원전의 안전성에 대한 대 국민 이해 및 신뢰 회복에 이바지 하고자 한다. 또한 최대허용농도를 기준으로 삼던 기존의 방식이 퇴색하고 ALI［l］를 이용한 국내 실정에 맞는 식품 중 허용농도 설정의 필요성이 대두되고 있는 현 실정을 감안하여 ALI를 이용하여 식품 중 최대허용농도를 설정하고자 한다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1997.05a
• /
• pp.108-113
• /
• 1997

하나로(HANARO)를 이용하여 핵분열 방법으로 진단용 방사선원인 $^{99m}$ Tc의 모핵종인 Mo-99를 생산할 경우, HEU 및 LEU UO2 표적이 사용될 수 있다. 표적연료로서 HEU(93w/o $^{235}$ U)가 LEU(19.75w/o $^{235}$ U)에 비해 생성수율(Ci/gU)이 높게 나타났으며 제품의 질(quality)을 좌우하는 비방사능(Ci$^{99}$Mo/gMo)은 같게 나타났다. HEU가 같은 Mo-99의 방사능량을 얻기 위해서는 우라늄 장전량이 적어지므로 폐기물측면과 용해측면에서 이득이나 농축도를 고려하면, 큰 이득이 발생하지 않으므로 하나로에 LEU를 사용하는 것도 타당하다 할 수 있다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1997.10a
• /
• pp.363-368
• /
• 1997

PWR 원전에서는 계획예방 정지운전시 효과적인 정지수화학 제어에 의해 일차계통 방사능 준위를 감소시키고 작업종사자의 피폭을 최소화하기 위해 정지운전 자료에 대한 보다 정확한 해석이 필요하다. 본 연구에서는 국내 PWR 원전 주기(A호기의 I 및 II주기와 B호기의 II주기)별 정지수화학 특성을 SCALP(Shutdown chemistry CALculation Program)프로그램으로 계산하고 정지운전 기간중 일차냉각재계통에서 제거되는 방사능량에 영향을 미치는 정지수화학 특성을 주요 인자별로 평가하였다.

• The Korean Journal of Nuclear Medicine Technology
• /
• v.18 no.1
• /
• pp.98-103
• /
• 2014

Purpose: The effective half life of I-131 is useful to calculate radiation dose, period of hospitalization, and exposure dose of surrounding people from patient. However, it is difficult to measure. This study estimates the effective half life in whole body and thyroid in using of value of residual radioactivity obtained from the early and delay images of Dual time I-131 whole body scan. Also, the correlations between the effective half life and serum creatinine, GFR, and administration dose were investigated in this study. Materials and Methods: The targets were 50 patients administration high dose of I-131 from February to August in 2013, having normal range of serum creatinine and over $30{\mu}IU/mL$ of TSH levels. After administration radioactive I-131, the early scan in the 3rd day and the delay scan in the 5-6th days were performed. To measure the residual radioactivity in the whole body and thyroid, ROI was set and then background radioactivity was corrected to estimate. The effective half life was estimated by calculating the ratio of measured values between the early and delay images. To compare the effective half lives of the whole body and thyroid, it was analyzed by Independent t-test, and each correlation of the effective half life, GFR, serum creatinine, and the dose of administration were analyzed by calculating the pearson's correlation coefficient. All of the analysis were determined to be statistically significant when P<0.05. Results: The effective half life of the whole body was $17.06{\pm}5.50$ hours and of the thyroid was $17.22{\pm}5.41$ hours. The two effective half life did not show significant difference (P=0.887). As the value of GFR was increased, the effective half life of whole body (r=-0.407, P=0.003) and of thyroid (r=-0.473, P=0.001) were significantly decreased; as the value of serum creatinine was increased, the effective half life of whole body (r=0.309, P=0.029) and of thyroid (r=0.371, P=0.008) were significantly increased. In the administration dose, effective half life did not have correlations. Conclusion: The effective half life of I-131 of patients treated for their thyroids were estimated only by using the images of Dual time I-131 whole body scan. Also, the correlations with the effective life, GFR, and serum creatinine were examined. This study might be utilized for a study on optimization for the period of hospitalization of patients treated by high dose of I-131 and on evaluation for internal absorbed dose of MIRD schema in application of the effective half life.