파이로 공정 세라믹 폐기물을 위한 처분용기의 설계, 제작 방안, 그리고 기능 평가 Design, Manufacturing, and Performance estimation of a Disposal Canister for the Ceramic Waste from Pyroprocessing원문보기
현재 한국원자력연구원에서는 국내에 축적된 사용후핵연료 문제를 해결하기 위해서 건식재처리공정(pyroprocess)을 개발 중에 있다. 건식재처리 공정에서는 상당량의 고준위 염폐기물이 발생되며, 이는 곧 세라믹 결합제로 고화된다. 고화된 세라믹 폐기물은 안전한 금속 처분용기에 밀폐된 후, 인간생활환경과 격리될 예정이다. 본문에서는 고준위 세라믹폐기물을 처분하기 위한 처분용기의 개발에 관한 전반적인 내용을 다루고 있으며, 특히 처분용기의 설계 요건, 용기의 구성, 용기의 제작, 용기의 부식저항성, 방사선 차폐, 구조적 안전성 등에 대해 논의하고자 한다. 완성된 처분용기는 오랜 기간 동안 방사성 핵종의 누출이 없이 열적, 기계적, 화학적, 생물학적 공격에도 안전한 것을 목적으로 한다.
현재 한국원자력연구원에서는 국내에 축적된 사용후핵연료 문제를 해결하기 위해서 건식재처리공정(pyroprocess)을 개발 중에 있다. 건식재처리 공정에서는 상당량의 고준위 염폐기물이 발생되며, 이는 곧 세라믹 결합제로 고화된다. 고화된 세라믹 폐기물은 안전한 금속 처분용기에 밀폐된 후, 인간생활환경과 격리될 예정이다. 본문에서는 고준위 세라믹폐기물을 처분하기 위한 처분용기의 개발에 관한 전반적인 내용을 다루고 있으며, 특히 처분용기의 설계 요건, 용기의 구성, 용기의 제작, 용기의 부식저항성, 방사선 차폐, 구조적 안전성 등에 대해 논의하고자 한다. 완성된 처분용기는 오랜 기간 동안 방사성 핵종의 누출이 없이 열적, 기계적, 화학적, 생물학적 공격에도 안전한 것을 목적으로 한다.
A pyroprocess is currently being developed by KAERI to cope with a highly accumulated spent nuclear fuel in Korea. The pyroprocess produces a certain amount of high-level radioactive waste (HLW), which is solidified by a ceramic binder. The produced ceramic waste will be confined in a secure disposa...
A pyroprocess is currently being developed by KAERI to cope with a highly accumulated spent nuclear fuel in Korea. The pyroprocess produces a certain amount of high-level radioactive waste (HLW), which is solidified by a ceramic binder. The produced ceramic waste will be confined in a secure disposal canister and then placed in a deep geologic formation so as not to contaminate human environment. In this paper, the development of a disposal canister was overviewed by discussing mainly its design premises, constitution, manufacturing methods, corrosion resistance in a deep geologic environment, radiation shielding, and structural stability. The disposal canister should be safe from thermal, chemical, mechanical, and biological invasions for a very long time so as not to release any kind of radionuclides.
A pyroprocess is currently being developed by KAERI to cope with a highly accumulated spent nuclear fuel in Korea. The pyroprocess produces a certain amount of high-level radioactive waste (HLW), which is solidified by a ceramic binder. The produced ceramic waste will be confined in a secure disposal canister and then placed in a deep geologic formation so as not to contaminate human environment. In this paper, the development of a disposal canister was overviewed by discussing mainly its design premises, constitution, manufacturing methods, corrosion resistance in a deep geologic environment, radiation shielding, and structural stability. The disposal canister should be safe from thermal, chemical, mechanical, and biological invasions for a very long time so as not to release any kind of radionuclides.
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제안 방법
In the design premises, the required life-time of a canister, the expected maximum static and dynamic loads, the maximum temperature at the canister surface, the permissible leak rate on the canister, the maximum dose rate at the canister surface, and the multiplication factor (Keff) were discussed to design a reliable disposal canister.
Such ceramic waste should be disposed of at a depth of several hundreds of meters below the surface. In this paper, an overview of disposal canister development for the ceramic waste was introduced, mainly regarding its design premises, constitution, manufacturing, corrosion resistance, radiation shielding, and structural stability.
The structural safety of a disposal canister was estimated using a computational analysis. For a lifting operation, the analysis results had satisfied the standard criteria (yield strength) of 45 MPa for both normal and deceleration cases with a safety factor of 2.
KAERI has developed a geological disposal system reflecting the geological conditions in Korea. This paper introduces the development of a disposal canister for ceramic waste, concerning its design premises, canister design, manufacturing, corrosion resistance, radiation shielding, and structural stability. Ceramic waste contains a small amount of long-lived radionuclides such as TRUs.
대상 데이터
Only 2 waste blocks are placed in a storage canister to make 120 kg of total weight. A commercially available stainless steel 304 L tube (KS250A Sch. 5S) with a 3.4 mm thickness is selected for the cylindrical body. Stainless steel 304 L plates with 5 mm thickness are used for the bottom and lid plates [2].
The dimensions of the disposal canister are D 103 cm × H 173 cm, and the total weight is about 7.2 tons.
The disposal canister dimension was designed to be D 103 cm H 173 cm, and the total weight is about 7.2 tons. The heat power per disposal canister was 594 W.
Environmental corrosion tests were performed for various coppers in a simulated repository condition in a laboratory. The test specimens were placed between Gyeongju compacted bentonite blocks in a waterpermeable titanium vessel, and then immerged in groundwater collected from KURT. The results of a 2-year test showed that all the coppers exhibited extremely low corrosion rates of less than 1.
이론/모형
079 103 (neutrons/sec), respectively, for the 44 energy groups. The Flux-to-Dose factor of ICRP-74 was used for the dose conversion. Dose calculations for a disposal canister were performed, the results of which were given in Table 2.
성능/효과
The corrosion behavior of the coating copper was studied to know if it can resist environmental corrosion for 1,000 years at a deep geologic condition. As a result of several corrosion tests, it was concluded that the copper formed by cold spray coating is not much different in corrosion behavior compared with other common coppers. A long-term corrosion test was being performed at KURT, simulating a deep geological repository condition.
Several immersion tests were performed for the copper specimens in an active environment such as a concentric HCl solution, humid air, and seawater. The results of the tests indicated that the coating copper was slightly more vulnerable to corrosion than normal coppers such as extruded and forging coppers. However, the suppression of corrosion was detected for the coating coppers as in the other copper specimens according to the results of the humid air test.
참고문헌 (12)
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Choi, Heui-Joo, Minsoo Lee, Jong Youl Lee, "Preliminary conceptual design of a geological disposal system for high-level wastes from the pyroprocssing of PWR spent nuclear fuels", Nuclear Engineering and Design, 241, pp 3348-33 (2011)
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