| 摘要(英) |
Nuclear power which is used as each countrasies one of the main sources of electricity, but the Nuclear power plant produces highly radioactive sSpent nNuclear fFuel eventually., tThe fuel rods haveinside nuclear half-life of thousands or even hundreds of thousands of years, and . Tthe decay of the heat generated by spent nuclear fuel in decay process, will form aaffect the environment in a certain range of temperature field effect. Thus, most countries use the concept of Internationally, the use of nuclear fuel for the final disposal of the nuclear fuel infinal use of ”deep geological disposal” , and the migration of radioactive nuclei was blocked bywith Engineered Barrier System (EBS) to reach the completely isolatedtion from with the human life circle design goals. TheOne of the main functionobjective of EBS the final disposal site is the use ofapplying the buffer material with the functional properties including high expansion potential, low hydraulic conductivity characteristics, appropriate thermal conductivity, and hysteresisdecreasing nuclear migration ability to block and delay the migration of highly radioactive nuclear species, and t. The evolution of near-field and far-field in deep-site treatment of radioactive wasteEBS, however, isare mainlystill affected by four factors, including Thermal, Hydraulic, Mechanical, and Chemical and other factors, influences. Tthese factors are often two or more interactionsed, referred to as T-H-M-C coupling effect, and thus affecting the fexpected functionality of the final disposal of the expected function.
In this study, the experiment was divided into two parts for the T-H coupling effect. First, we use the TDR time domain reflection (TDR) method tois employed to monitor the electrical properties of SPV200 bentonite, as well as the improvement of the TDR sensor. This research haveThen a small scale laboratory experiment and a the related simulation analysis of the re-saturation of bentonite state under T-H coupling of were conductedthe groundwater around the near-field environment. The second part is to study the relationship between the decay heat generated by the waste tank and the water-thermal coupling(T-H coupling) state formed by the groundwater entering the near-field environment. Three TDR sensors with a resolution of 1 cm were embedded in the bentonite samples. The samples were immersed in 25 ℃, 40 ℃, 60 ℃ three kinds of constant temperature water tank system for 120 hours to remove and observe the test Body flooding condition.
SPV200 bentonite electrical properties of the testwas found to have high electrical conductivitythat in as high water content bentonite, TDR wave with theand temperature increase. increase began to wave attenuation phenomenon, In this study,T the uses of plastic wrap and heat shrinkable two kinds ofas coating materials for the TDR probe were therefore proposed to monitor the layer volumetric water content of the bentonite as the re-saturation experiment. The results stated that insulating materials for tungsten steel bar sensor surface insulation treatment. Insulation treatment, the test found that plastic wrap tungsten steel rods have good insulation capacity and the amount of dielectric constant measured close to the SPV200 bentonite curve, so choose plastic film insulation tungsten steel bar under different temperature systems under the layered water content monitoring experiment.the plastic wrap can maintain the sensitivity of the measurement.
In the re-saturation experiment of bentonite under T-H couplingstratified water content monitoring experiment, it was observed that the volumeetric water content of the bentonite in the bottom layer was higher than that of the theoretical saturated bentonite volume water contentone of (47%) when the bentonite was immersed from the bottom in the 25 ℃ and 40 ℃ systems. The reason is that the bentonite has high swelling ability, the volume of Bentonite expansion after water absorptionre-saturated. In the volume of the fixed mold, tThe bottom lower layer of high degree of saturated bentonite extruded upper layer of low saturation bentonite, resulting in bentonite extrusion deformation,. tVhe poreoid volume and dry densitysoil particle volume changes. TheT trends of the displacement and saturation of the bentonite sample isare consistent with thatthe results of the ABAQUS finite element analysis, . tThe dry density is proportional to the relative displacement, whichwhile it is inversely proportional to the saturation and porevoid ratio. It is showsn that the stratification of this study The moisture content monitoring and measuring systemusing TDR canis effectively carry out the monitoring of the volume water content of bentonite test specimen in T-H coupling small scale experiment. |
| 參考文獻 |
王雅薇，(2008)，「緩衝材料在熱/水力耦合作用下溫度分布與水力傳導性研究」，國立中央大學，碩士論文。
莊怡芳，(2008)，「未飽和緩衝材料吸力與水力傳導度推求及再飽和行為」，國立中央大學，碩士論文。
行政院原子能委員會，(2010)，「放射性物料管理法」，行政院原子能委員會放射性物料管理局，華總一義字第09100248760號。
林伯聰，(2013)，「國際高放射性廢棄物最終處置場址技術準則之研究」，行政院原子能委員會放射性物料管理局，委託研究計畫研究報告。
黃偉慶，(2014)，「用過核子燃料深層地質處置場近場緩衝材料耦合效應研析」，行政院原子能委員會放射性物料管理局，委託計畫研究期末報告。
賈善坡、冉小豐、王越之、肖桃李、譚賢君，(2012)，「變形多孔介質溫度– 滲流– 應力完全耦合模型及有限元分析」，岩石力學與工程學報，第31 卷。
蔡家恩，(2016)，「用過核子燃料最終處置場緩衝材料之熱-水耦合實驗及模擬」，國立中央大學，碩士論文。
李冠宏，(2016)，「最終處置場近場環境對緩衝回脹壓力之影響」，國立中央大學，碩士論文。
放射性廃棄物研究，(2009)，「緩衝材大型試験設備 (BIG-BEN) における熱-71<-応力連成試験」，Vol.16 No.1。
原子力バックエンド研究，(1994)，「緩衝材の地球化学プロセスに着目した熱－水－化学連成挙動に関する工学規模の人工バリア試験と解析評価」，Vol. 1， No. 1。
総合資源エネルギー調査会，(2015)，「地層処分技術 WG 第 12 回会合参考資料」，総合資源エネルギー調査会電力・ガス事業分科会 原子力小委員会。
JNC，(1999)，「熱的特性の緩衝材仕樣に対する影響」，TN 8400-99-052，核燃料サイクル開發機構。
PNC，(1992)，「緩衝材の熱物性試験」，TN 1410-92-052，動力炉・核燃料開発事業团。
JAEA-Data-Code，(2016)，「幌延深地層研究計画における人工バリア性能確認試験計測データ集」，幌延深地層研究センター。
JAEA-Data-Code，(2016)，「幌延深地層研究計画における人工バリア性能確認試験－大口径掘削機の開発、模擬オーバーパック、緩衝材および埋め戻し材の製作」，幌延深地層研究センター。
JAEA-Data-Code，(2016)，「幌延深地層研究計画における人工バリア性能確認試験-平成27年研究計畫成果、平成28年研究計畫」，幌延深地層研究センター。
ASTM (2014). “Standard Test Method for Determination of Thermal Conductivity of Soil and Soft Rock by Thermal Needle Probe Procedure” D5334.
Baker, J.M., and Allmaras, R.R. (1990). “System for automation and multiplexing soil moisture measurement by time-domain reflectometry.” Soil Sci Soc. Am J., Vol. 54, pp. 1-6.
Chen, L., Liu, Y.M., Wang, J., Cao, S.F., Xie, J.L., Ma, L.K., Zhao, X.G., Li, Y.W., and Liu, J. (2014). “Investigation of the thermal-hydro-mechanical (THM) behavior of GMZ bentonite in the China-Mock-up test.” Engineering Geology, Vol. 172, pp. 57–68.
Davis, J.L., and Annan, A.P. (1977). “Electromagnetic determination of soil moisture: progress report Ι.” Canadian Journal of Remote Sensing, Vol. 3, pp. 76-86.
Fabrice, D., Chao, L., and Lyesse, L. (2013). “THM coupling sensitivity analysis in geological nuclear waste storage.” Engineering Geology, Vol. 163, pp. 113–121.
Fälth B., and Hökmark H. (2006). “Mechanical and thermo-mechanical discrete fracture near-field analyses based on preliminary data from the Forsmark.” Simpevarp and Laxemar sites, SKB R-06-89, Svensk Kärnbränslehantering AB.
Tsang, C.F., Barnichon, J.D., Birkholzer, J., Li, X.L. Liu, H.H., and Sillen, X. (2012). “Coupled thermo-hydro-mechanical processes in the near field of a high-level radioactive waste repository in clay formations.” International Journal of Rock Mechanics & Mining Sciences, Vol. 49, pp. 31–44.
Heimovaara, T.J. (1993). “Design of triple-wire time domain reflectometry probes in practice and theory.” Soil Sci. Soc. Am. J., Vol. 57, pp. 1410–1417.
Hudsona, J.A., Stephanssonb, O., Anderssonc, J., Tsangd, C.F., and Jingb, L. (2001). “Coupled T–H–M issues relating to radioactive waste repository design and performance.” International Journal of Rock Mechanics & Mining Sciences, Vol. 38, pp. 143–161.
Kristensson O., and Hökmark H. (2007). “Prototype Repository. Thermal 3D modelling of Prototype Repository.” SKB IPR-07-01, Svensk Kärnbränslehantering AB.
Ledieu, J., De Ridder, P., and Dautrebande, A. (1986). “A method for measuring soil moisture by time domain reflectometry.” Journal of Hydrology, Vol. 88, pp. 319-328.
SKB (2009b). “Strategy for thermal dimensioning of the final repository for spent nuclear fuel.” Techical Report, R-09-04.
SKB (1999). “Deep repository for spent nuclear fuel: SR 97 post-closure safety.” SKB Technical Report 99-06-Main Report Summary. |
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