연속철근 콘크리트 포장(CRCP: Continuously Reinforced Cement Pavement)은 시멘트 콘크리트 포장 공법 중 하나이 다. 한국형 포장 설계법(KPRP: Korean Pavement Research Program)은 국내 실정에 맞게 개발된 도로 포장 설계법으 로, 2011년에 최초로 개발되었다. 현재 최신 버전은 2016년 4월에 발표된 것으로, 이후 약 9년간 업데이트가 이루어지지 않았다. 본 연구의 목적은 한국형 포장 설계법 내 기존 CRCP 해석 모듈을 분석하고 이를 개선하는 것이다. 또한, 본 연 구에서 개선된 CRCP 해석 모듈은 추후 개발 예정인 고속도로 역학적-경험적 포장 설계법(EXPD: EXpressway Pavement Design)에 적용될 예정이다. 기존 KPRP의 연속철근 콘크리트 포장 설계법은 과거의 기상 데이터를 이용하여 슬래브에 가해지는 환경 하중에 의한 응력을 계산한다. 포장이 미래의 공용수명 20년을 버텨야 하나, 과거의 기상 데이터를 통해 계산된 환경 하중에 의한 응 력을 고려하도록 설계법이 구성되어 있는 현실이다. 과거의 기상 데이터가 아닌 기후변화 예측 모형을 통해 예측된 기상 데이터를 기존 포장 설계법에 적용한다면, 보다 타당한 공용성 해석 결과를 기대할 수 있을 것으로 예상된다. 국립기상 과학원에서 배포한 IPCC 6차 평가보고서(AR6) 대응 전지구 기후변화 전망보고서에서 제시한 최신 온실가스 경로(SSP, Shared Socioeconomic Pathways)에 따라 산출된 신규 전지구 기후변화 시나리오 4종 중에서 가장 최악의 시나리오인 SSP-8.5로 가정하였을 때에 예측된 기상 데이터를 이용하여 공용성 해석 결과인 펀치아웃(Punchout) 개수와 포장 두께 변화에 대하여 분석해보았다.

In the decommissioning site of Korean Research Reactor 1&2 (KRR-1&2), according to Low and Intermediate-level Radioactive Waste Disposal Acceptance Criteria of the Korea Radioactive Waste Agency (WAC-SIL-2022-1), characteristics of radioactive waste was conducted on approximately 550 drums of concrete and soil waste for a year starting from 2021. Among them, 50 drums of concrete waste transported and disposed to Gyeongju LILW disposal facility at the end of 2022. For the remaining approximately 500 drums of concrete and soil waste stored on-site, they were reclassified into two categories: permanent disposal grade and clearance grade. This classification was based on calculating the sum of fractions (SOF) per drum for each radionuclides. The plan is to dispose of around 200 drums in the permanent disposal grade and about 300 drums in the clearance grade by the end of 2023. Since concrete and soil decommissioning wastes are generated in large quantities over a short period with similar origins, they were grouped within five drums as suggested by the acceptance criteria. Mixed samples were collected from each group and used for radionuclide analysis. When utilizing mixed samples, three distinct samples are collected and analyzed for each group. The maximum value among these three radionuclide analysis results is then uniformly applied as the radionuclide concentration value for all drums within that group. Radioactive nuclides contained in similar types of radioactive waste with similar origins can be expected to have some statistical distribution. However, There has been no verification as to whether the maximum value among the three mixed samples exists within the statistical distribution or if it deviates from this distribution to represent a different value. In this study, we confirmed characteristics of radionuclide concentration distribution by examining and comparing radionuclide concentration distributions for radioactive wastes drum grouped for nuclear characteristic among 50 concrete wastes drum disposed in year 2022 and 500 concretes & soils drum scheduled for disposal (clearance or permanent disposal) in year 2023. In particular, when comparing tritium to other nuclides, it was observed that the standard deviation for the distribution of maximum values was approximately 318 times larger.

This study is done as a comparison analysis on existing studies on analysis and interpretations of solenoids. When there is no power in a solenoid valve, a flow passage is formed from a pressurized ports, Pc, to Ps, which are connected to a crankcase of a pressurizer. An inlet to Pc port is varied in three different sizes: 3.8 ㎜(Type-1), 4.0 ㎜(Type-2) and 4.2 ㎜(Type-3). It is determined that there will be changes in coolant flow into the solenoid valve and the flow properties from Pc port to Ps port are compared and analyzed. As the results, the flow demonstrates the maximum speed of 500 ㎧, 46 ㎧ and 433 ㎧ with 0.2 ㎫ for the inflow pressure and the maximum speed of 1400 ㎧, 129 ㎧ and 1200 ㎧ with 1.5 ㎫ for the inflow pressure.