High level radioactive waste (HLW) final disposal repository is faced thermos-hydro-mechanical - radioactive condition because it is placed over 500 m in depth and waste emits decay heats for decades. Repository will be operated around 100 years and will be closed after all the wastes are disposed. The integrity of engineered barriers including buffer, backfill, concrete plug and canister and natural barrier (natural rock mass) will be stood during operating periods. Monitoring sensors for concrete and rock mass is conducted using piezo based sensors such as accelerometer or acoustic emission (AE) sensors. Typical accelerometer for harsh conditions is commonly expensive and data/power cable can be a potential groundwater inflow and nuclide outflow path. The fiber optic accelerometer whose data and power cable are united and has limited volume. Therefore, it can be a potential alternative sensor of piezo based sensors. The temperature limits and accelerated tests for fiber optic sensors are conducted. Most of sensors gives a malfunction around 130°C. The results of these experimental tests give a possibility of communications in compacted bentonite buffer and will be utilized for the design of monitoring systems for the repository.

The high-level nuclear waste (HLW) repository disposes of high-level nuclear waste at a depth of 500 m to 1,000 m underground. Structural health monitoring must be accompanied by the complex environmental conditions of high temperature, high humidity, radiation, and mechanical stress. A thermocouple for measuring temperature, total stress meter and pore pressure meter for measuring stress and water pressure, relative hygrometer and electrical resistivity sensor (TDR or SUS) for measuring humidity, accelerometer for measuring crack signals, and strain gauge for measuring displacement are used. For safety, after disposing of HLW in the HLW repository, access to the disposal tunnel gets blocked, making it impossible to replace or remove the monitoring sensors. So, it is necessary to evaluate the effect of the HLW repository’s environmental conditions on the monitoring sensors and enhance their durability through quantitative life evaluation and shielding. Before evaluating the life of accelerometers and strain gauges used in the HLW repository, an experimental study is conducted to determine failure modes and failure mechanisms under radiation conditions, which are unique environmental conditions of the HLW repository.

In the nuclear environment, sensors ensure safety, monitoring, and operational efficiency under various operating conditions. These sensors come in various forms, each tailored to specific purposes, including nuclear safety and security, waste treatment and storage, gas leak detection, temperature and humidity monitoring, and corrosion detection. Ensuring the longevity of sensors without the need for frequent replacements is a vital goal for researchers in this field. This paper explores materials that can act as shields to protect sensors from harsh environmental conditions (high radiation and temperatures) to enhance their lifetime. The types of material that had been explored were divided into categories: metal and non-metal. Fourteen types of metal and seven different plastic materials were studied and focused on their characteristics and current applications. Considering properties like melting point, intensity, and conductivity, plastic materials are chosen to be examined as sensor shielding material. A preliminary experiment was conducted to verify signal characteristics changes by shielding material. Metal material and plastic material each were placed in the middle of the granite and the target sensor. The result showed that when metal is between the granite and the sensor, the density and impedance are higher in granite than in the metal. This leads to signal attenuation and a shift in resonance frequency, while plastic does not. Therefore, PPS (Polyphenylene sulfide) and PAI (Polyamide-imide) have lower density and impedance than granite while also possessing heat, moisture, and radiation resistance for effective shielding.

The high-level nuclear waste (HLW) repository is a 500-1,000 m deep underground structure to dispose high-level nuclear waste. The waste has a very long half-time and is exposed to a number of stresses, including high temperatures, high humidity, high pressure These stresses cause the structure to deteriorate and create cracks. Therefore, structural health monitoring with monitoring sensors is required for safety. However, sensors could also fail due to the stresses, especially high temperature. Given that the sensors are installed in the bentonite buffer and the backfill tunnel, it is impossible to replace them if they fail. That’s why it is necessary to assess the sensors’ durability under the repository’s environmental conditions before installing them. Accelerated life test (ALT) can be used to assess durability or life of the sensors, and it is important to obtain the same failure mode for reliability tests including ALT. Before conducting the test, the proper stress level must be designed first to get reliable data in a short time. After that, acceleration of life reduction with increasing temperature and temperature-life model should be determined with some statistical methods. In this study, a methodology for designing stress levels and predicting the life of the sensor were described.

The design of the high-level radioactive waste (HLW) repository is made for isolating the HLW from the groundwater system by using artificial and natural barriers. Granite is usually considered to be a great natural barrier for the HLW repository in various countries including Sweden, Canada, and Korea due to its low hydraulic permeability. However, many fractures that can act as conduits for groundwater and radionuclides exist in granite. Furthermore, the decay heat generated by the HLW can induce groundwater acceleration through the fracture. Since the direction, magnitude, and lasting time of the heat-induced groundwater flow can be differed depending on the fracture geometry, the effect of fracture geometry on the groundwater flow around the repository should be carefully analyzed. In this study, groundwater models were conducted with various fracture geometries to quantify the effect of various properties of fractures (or fracture networks) on the heat-induced groundwater flow. In all models, the pressure around the repository only lasted for a short period after it peaked at 0.1 years. In contrast, the temperature lasted for 10,000 years after the disposal inducing the convective groundwater flow. Single fracture models with different orientations were conducted to evaluate the variations in groundwater velocities around the repository depending on the fracture slope. According to the results, the groundwater velocity on the fracture was the fastest when the regional groundwater flow direction and the fracture direction coincided. In double fracture models, various inclined fractures were added to the horizontal fracture. Due to the intersecting, the groundwater flow velocity showed a discontinuous change at the intersecting point. Lastly, the discrete fracture network models were conducted with different fracture densities, length distributions, and orientations. According to the modeling results, the groundwater flow was significantly accelerated when the fracture network density increased, or the average fracture length increased. However, the effect of the fracture orientation was not significant compared to the other two network properties.

Extensive studies have been conducted on thermal conductivity of bentonite buffer materials, as it affects the safety performance of barriers engineered to contain high-level radioactive waste. Bentonite is composed of several minerals, and studies have shown that the difference in the thermal conductivity of bentonites is due to the variation in their mineral composition. However, the specific reasons contributing to the difference, especially with regard to the thermal conductivity of bentonites with similar mineral composition, have not been elucidated. Therefore, in this study, bentonites with significantly different thermal conductivities, but of similar mineral compositions, are investigated. Most bentonites contain more than 60% of montmorillonite. Therefore, it is believed that the exchangeable cations of montmorillonite could affect the thermal conductivity of bentonites. The effect of bentonite type was comparatively analyzed and was verified through the effective medium model for thermal conductivity. Our results show that Ca-type bentonites have a higher thermal conductivity than Na-type bentonites.

기존의 확률론적 안전성 평가의 신뢰도 제고를 위하여 잘 알려진 입력 파라미터의 일반적인 분포에 새롭게 측정된 신뢰도 있는 데이터를 결합하여 사후분포를 구할 수 있는 베이지안 업데이팅 방법론을 제안하였다. 마코프체인 몬테 칼로 샘플링 기법의 알고리듬을 통한 GoldSim 모듈도 개발하였다. 복수의 입력 파라미터의 사전분포에 대해 연속적으로 사후분포를 구 해낼 수 있는 베이지안 업데이팅이 가능하도록 개발된 이 모듈을 GoldSim 템플릿 형태의 기존의 GSTSPA 프로그램으로 이행하여 보다 신뢰도 있는 확률론적 방사성폐기물 처분 시스템 안전성 평가가 가능하도록 하였다. 이는 기존에 존재하는 사 전분포의 일반적인 형태는 취하되 새롭게 얻어지는 실제 측정치나 전문가들의 의견을 기존의 분포에 적용하여 보다 더 높은 믿음을 갖는 입력 파라미터의 사후분포를 얻을 수 있게 한다. 균열암반 내 핵종 이동에 관련된 몇 개의 입력 파라미터의 사전분포의 세차례의 연속적 업데이팅을 통해 프로그램의 유용성도 예시하였다. 이 연구를 통하여 처분시스템과 같이 장기적 평가가 필요하고 넓은 모델링 지역을 가지며 측정된 입력자료가 부족한 경우 보다 더 믿음직한 방법으로 안전성 평가를 수행할 수 있는 것을 보였다.

심지층 처분시스템에서 완충재는 지하수 유입으로부터 처분용기를 보호하고, 방사성 핵종 유출을 저지하기 위한 중요한 방 벽의 하나이다. 이에 완충재는 장기 건전성, 낮은 수리전도도, 낮은 유기물의 함량, 높은 핵종저지능, 높은 팽윤성, 높은 열 전도도 등 기술적 요건을 충족시켜야 하며 이는 정량적 분석결과를 바탕으로 결정될 수 있다. 국내의 경우 한국원자력연구 원에서는 1997년부터 경주지역에서 생산되는 벤토나이트를 완충재 후보물질로 연구를 지속하고 있다. 본 논문에서는 최근 동일 지역에서 생산된 벤토나이트(KJ-II)의 7가지 물리적 및 화학적 특성을 평가하였다. 분석 결과, 국내산 벤토나이트의 몬 모릴로나이트 함량은 약 65% 정도이며, 벤토나이트는 Ca형 벤토나이트이다. 본 논문을 통해 완충재 후보물질의 성능평가 항목과 분석 방법에 대한 기준을 제시하고자 하였다.

고준위폐기물 처분장의 기본적인 기능은 단기간에 과도한 방사성핵종이 유출되는 것을 방지하는데 있다. 이를 위해서는, 처분시스템의 구성요소들과 관련된 많은 기술 기준이 개발되고 수립되어야 한다. 처분장 안전성평가는 합리적으로 단순화된 모델에 바탕을 두고 처분장의 미래 전개에 대한 정량적인 결과를 산출하므로 안전성평가는 기술기준의 하나로 간주되고 있다. 본문에서는 평가기간, 선량 제한치 및 평가의 불확실성 등을 중심으로 안전성평가와 관련된 주요국의 기술기준을 조사하였다. 특히, 미국의 기준을 조사하는 과정에서 안전성평가에서 도출된 peak dose가 선량 제한치를 충족하지 못하는 경우, 평가기간 및 peak dose에 대한 미국 규제당국의 접근방안은 참고할만한 가치가 있음을 알 수 있었다.