초록 ▼

고준위폐기물 기준처분시스템의 건전성과 처분안전성의 실험적 검증에 필수적인 실험적 연구가 수행되었다. 지하처분연구시설의 건설을 위한 연구와 부지 암반특성에 관한 연구가 수행되었으며, 이 결과를 바탕으로 총 연장 255m (진입터널: 180 m, 연구모듈: 75 m) 규모의 지하연구시설(KAERI Underground Research Tunnel, KURT)을 설계, 건설하였다. 공학적방벽의 열-수리-역학적 거동 실증연구에서는 엔지니어링 규모의 실증장치를 설계, 제작하였으며, 이를 이용하여 공학적방벽에서의 THM거동을 규명하고 HM 모

고준위폐기물 기준처분시스템의 건전성과 처분안전성의 실험적 검증에 필수적인 실험적 연구가 수행되었다. 지하처분연구시설의 건설을 위한 연구와 부지 암반특성에 관한 연구가 수행되었으며, 이 결과를 바탕으로 총 연장 255m (진입터널: 180 m, 연구모듈: 75 m) 규모의 지하연구시설(KAERI Underground Research Tunnel, KURT)을 설계, 건설하였다. 공학적방벽의 열-수리-역학적 거동 실증연구에서는 엔지니어링 규모의 실증장치를 설계, 제작하였으며, 이를 이용하여 공학적방벽에서의 THM거동을 규명하고 HM 모델의 해석기법을 개발하였다. 비산소 조건과 환원환경에서 균열암반을 통한 비수착성 및 양이온 핵종, 악티나이드 핵종의 이동 특성을 규명하였다. 처분안전성 평가에 사용될 화강암에 대한 주요 핵종들의 수착분배계수, 암체확산계수 및 사용후핵연료의 갭 및 입계 재고량을 측정하였다.

Abstract ▼

In this study, tile researches for the construction of the underground research tunnel, KURT which is essential to validate the integrity of reference high-level waste disposal system, and the safety of geological disposal were carried out. For a candidate site located at Korea Atomic Energy Researc

In this study, tile researches for the construction of the underground research tunnel, KURT which is essential to validate the integrity of reference high-level waste disposal system, and the safety of geological disposal were carried out. For a candidate site located at Korea Atomic Energy Research Institute, the surface investigation and the boring tests were tarried out to assess the suitability as a site for KURT. The basic concept and the design requirements were established. Based on them, KURT was designed and constructed. Before the construction, a test blasting was performed in order to evaluate the possible impact of noise and ground vibration from blasting on neighbor research facilities. During the construction, an preliminary in situ experiments to observe the characteristics of excavation disturbed zone was carried out. The tunnel deformation could be recorded by an automatic measuring system.
In the study on the thermal-hydro-mechanical behavior of engineered barrier system, it was intended to design and construct the engineering-scale test facility, and to investigate THM behavior of the engineered barrier system. The computer modeling and interpreting methodology for THM behavior were also developed. An experimental study was carried out in order to investigate the erosion phenomena of a compacted bentonite block by a flowing groundwater thorough a rock fracture and to evaluate quantitatively the amount of bentonite colloids and their generation properties generated at the interface of buffer and fractured rock in relevant repository conditions. In hydrothermal reaction tests, smectite-to-illite conversion was studied using a domestic bentonite, and it was intended to assess the longevity of buffer material under the disposal environment.
To investigate the migration and retardation of radionuclide through the rock fracture under anaerobic condition, the experiments on the migration of non-sorting and cationic nuclides, and actinides through a fracture in the large granite block were conducted. The migration experiments of uranium and colloid through a rock fracture were carried out by using a granite core with a natural fracture and a natural groundwater in a glove-box, and the experimental study on the retardation of uranium by fracture filling materials was also done.
The solubilities of actinides with a long lifetime in a domestic ground water condition were calculated by PHREEQC (V.2).
To provide the input parameter for safety assessment, the distribution coefficients and rock matrix diffusion coefficients of key radionuclides onto granite were measured in a Glove-Box. The gap and grain boundary inventories of soluble elements in the spent PWR fuels with high and low burn-ups were also measured.

목차 Contents

• 제 1 장 서론...34
• 제 2 장 지하처분연구시설...36
• 제 1 절 배경...36
• 제 2 절 부지 조사...39
• 제 3 절 설계...82
• 제 4 절 인허가...125
• 제 5 절 건설...127
• 제 6 절 지하암반 특성 규명...137
• 제 7 절 현장 실험...182
• 제 3 장 한국형처분시스템의 공학적방벽 거동 규명...216
• 제 1 절 한국형처분시스템 열-수리-역학적 거동 실증실험...216
• 제 2 절 완충재 침식 특성...311
• 제 3 절 벤토나이트 열수반응 특성...363
• 제 4 장 비산화 및 환원조건에서 균열암반을 통한 핵종이동 실증실험...392
• 제 1 절 비산화조건에서 균열암반을 통한 용질이동 특성...392
• 제 2 절 환원조건에서 암반 시추코아 균열을 통한 악티나이드 및 콜로이드 이동 특성...428
• 제 3 절 지하환경에서 악틴족 원소의 응해 특성...453
• 제 5 장 처분안전성평가 입력인자 측정...470
• 제 1 절 평형분배계수...470
• 제 2 절 Rock Matrix 확산계수...477
• 제 3 절 사용후핵연료의 갭 유출률...498
• 제 6 장 결론...506
• 참고문헌...508
• 부록 I. 지하처분연구시설 현장실험 프로그램...522
• II. 사용후핵연료의 gap 및 grain boundary내 Cs, Sr, I의 재고량...538