• Korean Journal of Optics and Photonics
• /
• v.20 no.4
• /
• pp.201-206
• /
• 2009

In this study, we have fabricated a fiber-optic radiation sensor for detection of tritium using inorganic scintillators and optical fibers. We have tested various kinds of inorganic scintillators such as $Gd_2O_2S$ : Tb, $Y_3Al_5O_{12}$ : Ce, and CsI : Tl to select the most effective sensor tip. In addition, we have measured the scintillating lights using a photomultiplier tube as a function of distance between sensor tips to the source with the different activities of hydride tritium. The final results are compared with those which are obtained using a surface activity monitor.

• 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 Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.3 no.2
• /
• pp.125-133
• /
• 2005

Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO) . A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEIIfTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.06a
• /
• pp.464-473
• /
• 2005

Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO). A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEWTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment.

• Transactions of the Korean hydrogen and new energy society
• /
• v.29 no.2
• /
• pp.226-234
• /
• 2018

Even though the nuclear power plants has many advantages, safety issues of nuclear power plants are crucial factors of reliable operation. A tritium detector is a useful sensor to analyze amount of exposed radiation from the nuclear power plants. Currently, concentration of underwater tritium is measured precisely but it takes very long time. Since electrolysis is extracted hydrogen from the coolant of nuclear power plant, it can motivate to develop new type of real-time sensor. In this study, Proton Exchange Membrane (PEM) electrolyzer is studied for candidate as preprocessor of real-time tritium detector. Characteristics of the unit PEM electrolyzer were experimentally investigated. A simulation model is developed to understand physical behavior of unit PEM electrolyzer under dynamic operation.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05b
• /
• pp.427-432
• /
• 1998

중수속의 삼중수소 제거 공정인 액상 촉매 교환 반응에서 중수의 촉매 표면 응축에 의한 성능 저하가 큰 문제의 하나로서 성능 저하를 감소시키기 위한 여러 가지 형태의 촉매탑이 고안 되었다. 본 연구에서는 membrane을 사용하여 중수와 촉매를 분리시킴으로써 촉매 성능 저하를 감소시킬 수 있는 촉매탑의 설계를 시도하였다. 세 가지 촉매탑이 고안되었는데 sheet type의 membrane을 사용한 multilayered type 과 double spiral type, hollow fiber membrane을 사용한 hollow fiber cartridge type 등이다. multilayered type은 구조가 단순하여 scale-up이 용이하고 double spiral type은 다른 type보다 유로의 blocking 문제가 작고 hollow fiber cartridge type은 최대의 비표면적을 가질 수 있다.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2010.05a
• /
• pp.85-86
• /
• 2010

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2009.11a
• /
• pp.443-444
• /
• 2009

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05c
• /
• pp.435-440
• /
• 1996

삼중수소 제거 공정에 이용되는 소수성 고분자촉매의 담체인 스티렌-디비닐벤젠 공중합체의 제조 특성을 실험하였다. 스티렌-디비닐벤젠 고분자담체의 제조시 담체의 표면 특성에 대한 중합용액의 안정화 영향을 실험한 결과 약 40~55$^{\circ}C$의 범위에서 2시간 이상 용액을 안정화 시키는 것이 가장 바람직하였다. 또한 후처리 방법은 담체를 건조시키기 전에 용매를 제거하는 방법이 가장 우수한 기공 특성을 나타내었다. 담체의 입자 크기는 계면활성제의 농도가 낮을수록 더 크게 생성되었지만 용액의 점도가 증가하면 계면활성제의 영향이 감소됨을 알 수 있었다.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
• /
• 2003.05a
• /
• pp.377-382
• /
• 2003

본 연구의 대상인 자체발광 유리관은 밀봉된 유리관 내의 삼중수소에서 방출되는 베타입자와 유리관 내벽의 형광체와의 발광반응 메카니즘을 이용한 것이다. 자발광체는 삼중수소의 자연 붕괴와 형광체의 열화에 의해서 형광 효율이 감소되어 자발광체를 제조한 날로부터 지속적으로 휘도가 줄어들게 된다. 본 연구에서는 자발광체 제조 시 형광체의 열화를 최소화하기 위하여 형광체 열화에 영향을 미치는 요소인 온도, 온도 유지 시간, 공정 시 필요한 분위기를 다꾸지 방법에 의한 실험계획법으로 3인자 3수준의 교호작용을 고려하여 형광체의 음극선 발광 특성을 검토하였다.