Hydraulic conductivity is a critical design parameter for buffers in high-level radioactive waste repositories. Most employed prediction models for hydraulic conductivity are limited to various types of bentonites, the main material of the buffer, and the associated temperature conditions. This study proposes the utilization of a novel integrated prediction model. The model is derived through theoretical and regression analyses and is applied to all types of compacted bentonites when the relationship between hydraulic conductivity and dry density for each compacted bentonite is known. The proposed model incorporates parameters such as permeability ratio, dynamic viscosity, and temperature coefficient to enable accurate prediction of hydraulic conductivity with temperature. Based on the results obtained, the values are in good agreement with the measured values for the selected bentonites, demonstrating the effectiveness of the proposed model. These results contribute to the analysis of the hydraulic behavior of the buffer with temperature during periods of high-level radioactive waste deposition.

The objectives of this paper are: (1) to conduct the thermal analyses of the disposal cell using COMSOL Multiphysics; (2) to determine whether the design of the disposal cell satisfies the thermal design requirement; and (3) to evaluate the effect of design modifications on the temperature of the disposal cell. Specifically, the analysis incorporated a heterogeneous model of 236 fuel rod heat sources of spent nuclear fuel (SNF) to improve the reality of the modeling. In the reference case, the design, featuring 8 m between deposition holes and 30 m between deposition tunnels for 40 years of the SNF cooling time, did not meet the design requirement. For the first modified case, the designs with 9 m and 10 m between the deposition holes for the cooling time of 40 years and five spacings for 50 and 60 years were found to meet the requirement. For the second modified case, the designs with 35 m and 40 m between the deposition tunnels for 40 years, 25 m to 40 m for 50 years and five spacings for 60 years also met the requirement. This study contributes to the advancement of the thermal analysis technique of a disposal cell.

The thermal evaluations for the conceptual design of the deep geological repository considering the improved modeling of the spent fuel decay heat were conducted using COMSOL Multiphysics computational program. The maximum temperature at the surface of a disposal canister for the technical design requirement should not exceed 100°C. However, the peak temperature at the canister surface should not exceed 95°C considering the safety margin of 5°C due to several uncertainties. All thermal evaluations were based on the time-dependent simulation from the emplacement time of the canister to 100,000 years later. In particular, the heat source condition was set to the decay heat rate and axial decay heat profile of the PLUS7 fuel with 4.0wt% U-235 and 45 GWD/MTU. The thermal properties of the granitic rock in South Korea were applied to the host rock region. For the reference design case, the cooling time of the SNF was set to 40 years, the distance between the deposition holes 8 meters and that between the deposition tunnels 30 meters. However, the peak temperature at the canister surface at 10 years was 95.979°C greater than 95°C. This design did not meet the thermal safety requirement and needed to be modified. For the first modified case, when the distance between the deposition tunnels was set to 30 meters, three cooling time cases of 40, 50 and 60 years and five distances of 6, 7, 8, 9 and 10 meters between the deposition holes were considered. The design with the distances of 9 and 10 meters between the deposition holes for the cooling time of 40 years and all five distances for 50 and 60 years were less than 95°C. For the second modified case, when the distance between the deposition holes was set to 8 meters, three cooling time cases of 40, 50 and 60 years and five distances of 20, 25, 30, 35 and 40 meters between the deposition tunnels were considered. The design with the distances of 35 and 40 meters between the deposition tunnels for the cooling time of 40 years, the distances of 25, 30, 35 and 40 meters for 50 years and all five distances for 60 years were less than 95°C. As a result, the peak temperature at the canister surface decreased as the cooling time and the distance between the deposition holes and the tunnels increased.

본 연구는 정확한 열환경 평가를 위해 옥외 공간에서 체감하는 열쾌적성과 미기후 모델링을 통해 산출된 열쾌적지수의 차이점을 확인하는 것을 목적으로 한다. 이를 위해 대구광역시에 위치한 대학 캠퍼스 두 곳을 대상으로 하여 열쾌적성을 평가하는 두 가지 방법론을 적용하고 분석 결과를 비교하였다. 첫 번째 방법은 현장 설문조사를 기반으로 하여 시민들의 열쾌적성 정보를 수집하는 것이며, 두 번째 방법은 미기후 모델인 ENVI-met을 활용하여 열쾌적지수(PMV)를 수집하는 것이다. 또한, 열쾌적성에 영향을 미치는 요인을 파악하고자 그늘의 특성과 토지피복 특성을 기준으로 캠퍼스 내 상세 대상지를 선정하고 이러한 요인이 열쾌적성에 미치는 영향을 분석하였다. 분석 결과, 두 대학의 분석 일시와 장소가 달랐으나 방법론별 유사한 양상이 나타났다. 먼저, 설문조사 결과 그늘의 양이 증가할수록 쾌적한 것으로 나타났으며, 토지피복의 종류별 특성과는 다른 결과가 나타났다. 다음으로 모델링 결과 전반적으로 설문조사 결과와 비슷한 양상이 나타나지만 동일한 그늘의 특성을 가지는 세부 대상지에서 토지피복이 열환경에 부정적인 영향을 미치는 피복일 경우 열쾌적지수가 더 높게 나타났다. 결론적으로 설문조사 결과와 미기후 모델링 결과 간에 차이가 존재하며, 정책 반영을 위한 열쾌적성 정보의 수집 시 현장 기반의 체감 더위 정보의 수집을 통해 정확한 정보를 활용할 필요가 있을 것으로 판단된다.

This study is to investigate fuel cladding temperature in a transport system for the purpose of developing a methodology for evaluating the thermal performance of spent fuel. Detailed temperature analysis in the transport system is important because the degradation mechanism of the fuel cladding is generally sensitive to temperature and temperature history. In such a system, the magnitude of the temperature change is determined by examining the temperature sensitivity of fuel assemblies and system components including fuel cladding temperature, considering the material properties, component specifications, component aging mechanism, and heat transfer mechanism. The sensitivity analysis is performed using heat transfer models by computational fluid dynamics for the horizontal transport system. The heat transfer within the system by convection, conduction and thermal radiation is calculated by thermal-hydraulic analysis code FLUENT. The calculation region is divided into a basket cell and a transport cask. The thermal analysis of the basket cell is for predicting the fuel cladding temperature. And the reason for analyzing the transport cask is to provide the boundary condition for the basket cell by reflecting the external environmental conditions. Here, the basket cell containing the spent fuel assembly is modeled on the homogeneous effective thermal conductivity. The purpose of this analysis is to evaluate fuel cladding temperatures for the following four main items. That is the effect of surface emissivity changes in basket due to the oxide layer of the fuel cladding, the effect of degradation of the canister backfill helium gas, the effect of fuel assembly position in basket cell on fuel cladding and basket temperatures in canister, and the effect of using the homogeneous effective thermal conductivity model instead of the fuel assembly in basket cell. As a result of the analysis, the maximum temperatures in basket cells are evaluated for the above four items. Thermal margins for each item are investigated for thermal performance requirements (e.g., peak clad temperature below 400oC).

본 연구에서는 벤토나이트의 변질을 모사하기 위해 TOUGHREACT를 이용하여 열-수리-화학적 개념 모델링을 수행하였다. 모델링 결과 벤토나이트의 포화도는 지속적으로 증가하여 약 10 년 후에 포화상태에 도달하였다. 또한 온도는 급격히 증가 하여 0.5 년 이후에는 구리관으로부터 거리에 따라 일정한 온도 구배가 유지되었다. 이러한 열-수리 조건 변화에 따라 화학 적으로는 경석고와 방해석의 변질이 주로 발생하였다. 경석고와 방해석은 지하수가 유입됨에 따라 지속적으로 용해되었으 나, 온도가 높은 구리관 인근에서는 침전하는 경향을 보여주었다. 또한 경석고와 방해석의 침전으로 인해 구리관 인근의 공 극률과 투과도가 감소하였다. 확산 상수 변화에 대한 모델링 결과 경석고와 방해석의 변질은 확산 상수에 매우 민감하였으 며, 이는 결과적으로 수리적 특성인 공극률과 투과도에 영향을 미치고 있었다. 본 연구는 고준위 방사성폐기물 처분장 안전 성 연구에 기초적인 자료를 제공해 줄 것으로 판단된다.

반도체 소자에 정전기 방전으로 인한 소자내의 온도 상승을 알기 위해 열전달 방정식으로부터 열모델을 유도하였다. 그리고 열파괴 문턱전류를 얻고 시간에 따른 온도 변화를 열모델로부터 해석하였다. 여기서 유도한 열모델은 Wunsch-Bell모델에 지수 항을 추가한 형태이다. 이 모델의 유효성을 증명하기 위해 실험결과와 비교한 결과 매우 잘 일치하였으므로 이 열모델의 함수는 입력보호회로의 반도체소자를 설계하는데 매우 유용하다.

This paper presents a mathematical model on the longitudinal mid-span extension of the Tamar Bridge, UK by using 6 months data of temperatures and an extension starting from July 2010. Linear models of temperature input-extension output were identified for all the combinations of input temperatures. The model using two temperatures, one temperature on the top of the mid-span section and the other on the bottom, was found to be the best with the fitness value 95.9% while single-temperature input models had maximum fitness 80%. This observation might be explained by the temperature gradient at the section: in the existence of the temperature gradient, two temperatures in the section may represent the temperature distribution of the section well while a single temperature can't. A further study needs to be carried out to verify it by a thermal simulation on a Finite Element model of the bridge.