Carrageenan 유도 관절염에 대한 灸律 藥鍼의 진통작용

구성태,신종근,최윤영,송정방,김재효,김경식,손인철 한국전통의학연구소 2006 한국전통의학지 Vol.15 No.1

Objectives: This study was produced to examine the effects of moxibustion that had been played important role to traditional oriental medical treatment on disease. Recently, it was reported that moxi-tar which is generated in the process of moxibustion as burning combustibles decreased nitric oxide(NO) and inducible NO synthase (iNOS) generation in cellular experiments. Methods: Carrageenan-induced arthritis rat model was used to test the effect of moxi-tar as a chronic pain model. Diluted moxi-tar was single injected in several acupoints or combined with electroacupuncture (1 ms, 2 Hz, and 2 mA) into contralateral ST36 acupoint for 30 min to assess the synergic effects. After the treatment, behavioral tests measuring stepping force were periodically conducted during the next 12 hours. Endogenous NO and iNOS, cyclooxygenase-2 (COX-2), and c-Fos protein expression in the spinal cord were examined on a rat model of carrageenan-induced arthritis. Results : After the induction of arthritis, rats subsequently showed a reduced stepping force of the affected limb for at least the next 4 days. The reduced stepping force of the limb was presumably due to a painful knee, since oral injection of indomethacin produced temporary improvement of weight bearing. Moxi-tar produced significant improvement of stepping force of the hindlimb affected by the arthritis lasting at least 9 hours. The magnitude of this improvement was equivalent to that obtained after an oral injection of 3 mg/kg of indomethacin and this improvement of stepping force was interpreted as an analgesic effect. Moxi-tar produced the improvement of stepping force of the affected hindlimb in a dose-dependent manner. Both NO production and iNOS, COX-2 protein expression increased by arthritis were suppressed by moxi-tar. Moxi-tar on combination with electroacupuncture (EA) produced more powerful and longer lasting improvement of stepping force of the hindlimb affected by the arthritis than either moxi-tar or EA did. Conclusion : The present study suggest that moxi-tar produces a potent analgesic effect on the chronic knee arthritis pain model in the rat and that moxi-tar-induced analgesia modulate endogenous NO through the suppression of iNOS/COX-2 protein expression.

특수형 방사성 동위원소 운반캡슐의 안정성 평가

이주찬,서기석,구정회,방경식,한현수,박성원 대한방사선 방어학회 2001 방사선방어학회지 Vol.26 No.1

특수형 방사성물질 운반캡슐은 국내외의 수송관련 법규에 규정된 기술기준을 만족하도록 설계, 제작되어야 한다. 본 연구의 목적은 하나로에서 생산된 192Ir 특수형 동위원소 운반캡슐의 건전성을 평가하는데 있다. 법규에서 규정된 낙하시험, 타격시험, 굽힘시헝 및 가열시험조건에 대한 안전성 시험을 수행하였으며, 각각의 시험 전후에 누설시험을 수행하였다. 또한, 안전성시험과 더불어 컴퓨터코드를 이용한 전산해석을 수행하여 안전성시험 전에 시험결과에 대한 예측자료로 활용되었다. 낙하시험 및 가열시험 결과 캡슐 표면에서 약간의 흠집과 변형이 발생하였으나, 각각의 시험에서 평가기준이 되는 캡슐의 손상이나 용융 등은 발생하지 않았다. 또한 각 시험 후 수행한 누설시험 결과 누설이 발생하지 않았다. 따라서 특수형 방사성물질 운반캡슐은 법규에서 규정하는 기술기준을 만족하도록 설계, 제작되었음이 입증되었다. All of sealing capsules to transport a special form radioactive material should be designed and fabricated in accordance with the design criteria prescribed in IAEA standards and domestic regulations. The objective of this study is to demonstrate the safety of a shipping capsule for 192Ir special form radioisotope which produceed in the HANARO. The safety tests were carried out for the impact, percussion, bending and heat test conditions. And leakage tests were carried out before and after the each test. Also, the safety analyses were performed using computer codes in order to verify the test results. The capsule showed slight scratches and deformation, and maintained its structural and thermal integrities in all tests without any severe damage or melting. It also met the allowable limits of leakage rate after earth test. Therefore, it has been verified that the capsule was designed and fabricated to meet all requirements for the special form.

Drying Experiments Using a Lab-scale Vacuum Drying Apparatus

Kyoung-Sik Bang,Seung-Hwan Yu,Kyung-Wook Shin,Nam-Hee Lee,Gyung-Sun Chae 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.1

There is a need to develop a quantitative residual water measurement method to reduce the measurement uncertainty of the amount of residual water inside the canister after the end of vacuum drying. Therefore, a lab-scale vacuum drying apparatus was fabricated and its characteristics were evaluated by performing vacuum drying experiments based on the amount of residual water, vacuum drying experiments based on the surface area of residual water, and vacuum drying experiments based on the energy of residual water using the lab-scale vacuum drying apparatus. As a result of the vacuum drying experiments, if the surface area of water is the same, the greater the amount of water, the greater the energy of the water, so more energy is transferred to the surface of the water. Therefore, more water evaporated, and the average temperature of the remaining water was higher. The larger the surface area of the water, the more energy it takes to vaporize it, so the faster it dries and the faster the drying time. Before ice formed, energy was actively transferred by conduction heat transfer from the top, center, and bottom of the water to provide the energy needed for the water to evaporate from the surface. However, no energy was transferred from the water just before it turned into ice. When vacuum drying water, you can dry more water if you dry it slowly over a longer period of time. Therefore, by using a vacuum pump with a low flow rate, the pressure can be lowered slowly to prevent ice from freezing, thereby improving the drying quantity. It was evaluated that there was a good agreement between the energy used when water evaporated and the energy absorbed from the surroundings to within about 4%. Therefore, if the energy absorbed from the surroundings is known, it is possible to evaluate the amount of water evaporated in vacuum drying.

Drying Tests According to Pump Capacity and Canister Volume

Kyoung-Sik Bang,Ji-Hwan Lim,Seung-Hwan Yu,Kyung-Wook Shin,Nam-Hee Lee,Gyung-Sun Chae 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.2

When storing spent fuel in a dry condition, it becomes essential to ensure that any remaining moisture bound to the canister and spent fuel is effectively removed and stored within an inert gas environment. This is crucial for preserving the integrity of the spent fuel. According to the NRC- 02-07-C-006 report, it is advised to reduce pressure gradually or in incremental stages to prevent the formation of ice. In the context of vacuum drying, it is desirable to perform testing using a prototype model; however, utilizing a prototype model can be difficult due to budget constraints. To address this limitation, we designed and constructed a laboratory-scale vacuum drying apparatus. Our aim was to assess the impact of vacuum pump capacity on the drying process, as well as to evaluate the influence of canister volume on drying efficiency. The vacuum drying tests were carried out until the surface temperature of the water inside reached 0.1°C. In the tests focusing on vacuum pump capacity, vacuum pumps with capacities of 100, 200, 400, and 600 liters were employed. The outcomes of these tests indicated that smaller vacuum pump capacities resulted in increased evaporation rates but also prolonged drying times. In the case of drying tests based on canister volume, canisters with volumes of approximately 100 and 200 liters were utilized. The results revealed that larger canister volumes led to longer drying times and lower rates of evaporation. Consequently, if we were to employ an actual dry storage cask for vacuum drying the interior of the canister, it is anticipated that the process would require a substantial amount of time due to the considerably larger volume involved.

Thermal integrity tests of a shipping package using a slice model and a half-scale model

Bang, Kyoung-Sik,Yu, Seung-Hwan,Lee, Ju-Chan,Seo, Ki-Seog,Choi, Woo-Seok,Lee, Dong-gyu Elsevier 2018 Nuclear engineering and design Vol.338 No.-

<P><B>Abstract</B></P> <P>KORAD-B/II shipping packages, developed by the Korea Radioactive Waste Agency (KORAD), are used to transport C4 concrete packages, which are temporarily stored in the HANUL nuclear power plant. These packages must therefore meet the requirements of the Korea Nuclear Safety Security Commission Act 2017-56, the IAEA Safety Standard Series No. SSR-6, and US 10 CFR Part 71. The regulatory guidelines classify a KORAD-B/II shipping package as a Type B package, and state that this type of package must be able to withstand a temperature of 800 °C for a period of 30 min. It is desirable to use a full-scale model of a shipping package when performing tests to evaluate its integrity. However, performing a test using a full-scale model is costly. Therefore, to evaluate the thermal integrity of a KORAD-B/II shipping package, thermal tests were conducted using a slice model. For comparison, a thermal test was also carried out using a half-scale model. In the first thermal test using the slice model, the maximum surface temperature of the cask body was higher than the permitted maximum temperature limit because of incomplete combustion. In the second thermal test using the slice model and in the thermal test using the half-scale model, the maximum temperature of the cask body was lower than the permitted maximum temperature limit, thus proving that the thermal integrity of the KORAD-B/II shipping package could be maintained. The temperature results of the thermal test using the slice model were higher than those of the thermal test using the half-scale model. The effect of flame on a single-layer shipping package without neutron shielding, such as the KORAD-B/II shipping package, appears to be influenced more by a reduction in time rather than in size.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Thermal integrity of a shipping package using a slice model and a half-scale model is experimentally investigated. </LI> <LI> The maximum temperatures of the cask body and the containment seal were lower than the permitted maximum temperature. </LI> <LI> The sooty surface becomes a black body, thereby increasing the surface temperature. </LI> <LI> The effect of flame on a single-layer shipping package appears to be influenced more by a reduction in time rather than in size. </LI> </UL> </P>

Experimental Study on the Effect of a Metal Storage Cask and Openings on Flame Temperature in a Compartment Fire

Bang, Kyoung-Sik Korean Radioactive Waste Society 2020 방사성폐기물학회지 Vol.18 No.3

Compartment fire tests were performed using kerosene and Jet A-1 as fire sources to evaluate the relationship between flame temperature and opening size. The tests were performed for a fire caused by the release of kerosene owing to vehicle impact, and for a fire caused by the release of Jet-A-1 owing to airplane collision. The compartment fire tests were performed using a 1/3-scale model of a metal storage cask when the flame temperature was deemed to be the highest. We found the combustion time of Jet-A-1 to be shorter than that of kerosene, and consequently, the flame temperature of Jet-A-1 was measured to be higher than that of kerosene. When the opening was installed on the compartment roof, even though the area of the opening was small, the ventilation factor was large, resulting in a high flame temperature and long combustion. Therefore, the position of the opening is a crucial factor that affects the flame temperature. When the metal storage cask was stored in the compartment, the flame temperature decreased proportionally with the energy that the metal storage cask received from the flame.

Comparison of Fire Test Using Slice Model and Half-scale Model of the KTC-360 Transport Cask

Kyoung-sik Bang,Yun-Young Yang,Woo-Seok Choi 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.2

According to the ‘Basic Plan for High-Level Radioactive Waste Management (draft)’, the total amount of CANDU spent nuclear fuel is expected to be approximately 660,000 bundles. To safely and efficiently transport this amount to interim storage facilities, it is essential to develop a large-capacity transport cask. Therefore, we have been developing a large-capacity PHWR spent nuclear fuel transport cask, called the KTC-360 transport cask. According to the transport-cask related regulations, the KTC-360 transport cask was classified as a Type B package, and such packages must be able to withstand a temperature of 800°C for a period of 30 min. It is desirable to conduct a test using a fullscale model of a shipping package when performing tests to evaluate its integrity. However, it is costly to perform a test using a full-scale model. Therefore, to evaluate the thermal integrity of the KTC-360 transport cask, the fire test was conducted using a slice model. For comparison purposes, the fire test was also carried out using a 1/4 scale model. In the fire test using a slice model and in the fire test using a 1/4 scale model, the maximum temperature of the cask body was lower than the permitted maximum temperature limit. Therefore, the thermal integrity of the KTC-360 transport cask could be considered to be maintained. The temperature results from the fire test using a slice model were higher than those of the fire test using a 1/4 scale model. Therefore, the effect of flame on a transport cask without combustible materials, such as the KTC-360 transport cask, seems to be affected by the reduction in the time rather than the size reduction.

Thermal Test for Design Approval of the KTC-360 Transport Cask

Kyoung-sik Bang,Yun-Young Yang,Woo-Seok Choi 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.1

Currently, the HI-STAR 63 transport cask, developed to transport CANDU spent nuclear fuel from the wet storage pool to the dry storage facility which is called the MACSTOR/KN-400, has a transport capacity of 120 bundles, which is unfavorable when considering transportation costs and other related aspects. According to the ‘Basic Plan for High-Level Radioactive Waste Management (draft)’, the total amount of CANDU spent nuclear fuel is expected to be approximately 660,000 bundles. To safely and efficiently transport this amount to interim storage facilities, it is essential to develop a large-capacity transport cask. Therefore, we have been developing a large-capacity PHWR spent nuclear fuel transport cask, called the KTC-360 transport cask. According to the transport-cask related regulations, the KTC-360 transport cask was classified as a Type B package, and such packages need to maintain integrity under the normal transport and accident conditions described in these regulations. To prove the thermal integrity of this cask under the normal transport and accident conditions, high-temperature and fire tests were performed using a one-third slice model of an actual KTC-360 cask. The results revealed that the surface temperature of the cask was 62°C, indicating that such casks need to be transported exclusively. The highest temperature of the CANDU spent nuclear fuel was predicted to be lower than the melting temperature of Zircaloy-4, which was the sheath material used. Therefore, if normal operating conditions are applied, the thermal integrity of a KTC- 360 cask could be maintained under normal transport conditions. The fire test revealed that the maximum temperatures of the structural materials, stainless steel, and carbon steel, were 446°C lower than the permitted maximum temperatures, proving the thermal integrity of the cask under fireaccident conditions.

Forced Circulation Drying Test of Residual Water According to Pressure

Kyoung-Sik Bang,Ju-Chan Lee,Seung-Hwan Yu,Woo-Seok Choi,Kyung-wook Shin 한국방사성폐기물학회 2019 한국방사성폐기물학회 학술논문요약집 Vol.2019 No.10

기장연구로 신연료 운반용기 설계승인을 위한 화재시험평가

방경식(Kyoung-sik Bang),양윤영(Yun-young Yang),정길언(Gil-eon Jeong) 한국화재소방학회 2022 한국화재소방학회 학술대회 논문집 Vol.2022 No.춘계

기장연구로의 가동을 위해 필요한 핵분열성물질인 신연료를 원자력연구원에서 기장연구로까지 안전하게 운반하기 위한 신연료 운반용기는 over-pack, canister 및 내부 구조물로 구성되어 있다. 국내⋅외 운반용기 관련법규에 따르면 신연료 운반용기는 IP-2(F)형 운반용기로 분류된다. IP-2(F)형 운반용기는 운반사고조건인 800 ℃ 이상의 화염 속에서 30분 이상 견딜 수 있는 능력을 갖추어야 한다. 따라서, 신연료 운반용기가 800℃ 화재조건에서 건전성을 유지하는지 여부를 평가하기 위해 인허가 기관의 입회하에 화재시험을 수행하였다. 화재시험에 사용된 시험모델은 기장연구로 신연료 운반용기와 동일한 원형모델로서 화재시험에 앞서 정상운반조건인 1.2 m 낙하시험, 운반사고조건인 9 m 낙하시험 및 1 m 파열시험을 수행한 시험모델이다. 화재시험에서 시험모델의 온도를 측정하기 위해 over-pack 외부표면의 상부⋅중앙부⋅하부에 각 3개씩 9개, over-pack뚜껑에 2개를 부착하였으며, canister 내부표면의 상부⋅중앙부⋅하부에 각 3개씩 9개의 열전대를 부착하였다. 화재시험을 수행한 30분 동안의 평균 화염온도는 816 °C로 측정되었다. 화재시험에서 over-pack 외부표면의 최고온도는 화재시험을 시작한 시점에서 약 23분 경과한 후 809 °C로 측정되었으며, 뚜껑에서의 최고온도는 약 27분이 경과한 후 887 °C로 측정되었다. Canister 내부표면의 최고온도는 약 6시간이 경과한 후 135° 방향의 하부에서 330 °C로 측정되었으며, 45°방향에서 최고온도는 상부에서 257 °C로 측정되었고, 225° 방향에서 최고온도는 하부에서 257 °C로 측정되었다. 화재시험에서 측정된 canister 내부표면의 최고온도인 330 °C는 구조재인 스테인리스강의 구조 강도가 변화하지 않는 단기 노출 시의 허용온도인 538 °C보다 낮은 온도이다. 운반사고조건에서 기장연구로 신연료의 허용온도는 570 °C 이다. Canister 내부의 basket에 적재되는 신연료의 온도는 canister 내부표면에서 측정된 최고온도인 330 °C보다 낮을 것이다. 따라서, 800 °C 이상의 화염 속에서 30분 이상 동안 노출시키는 화재조건에서 운반용기 및 신연료의 열 적 건전성은 유지되는 것으로 판단된다.