台電核一廠已屆齡除役，故需將廠內用過核子燃料池中之用過核子燃料移放至乾式貯存系統進行中期貯存，台電公司引進NAC-UMS並請核研所依照本國法規將和NAC合作將其改進為INER-HPS，此套系統可貯存BWR燃料束，其具有燃料格架、密封鋼桶、混凝土護箱以及外加屏蔽等組件可透過空氣自然對流移除燃料產生衰變熱，並透過混凝土結構之隔絕降低其對環境造成的輻射劑量。
　　本研究針對INER-HPS進行全面地熱流分析，評估其最大允許之熱負載，並討論不同配置對系統造成的影響，也評估在不同的事件下，其系統內部熱流現象的變化;除此之外，為了因應未來可能遭遇之情形，並且確保本系統之熱流餘裕，本研究也針對特殊燃料進行評估，透過文獻回顧將特殊燃料之材料性質量化以利於本研究之進行，並且根據短週期冷卻完整燃料的結果進行配置之篩選以確保本研究計算結果之保守性。
　　研究結果顯示在適當地熱負載配置下，INER-HPS具有充足之餘裕可裝載各式用過核子燃料，本研究更於第五章末節引用實際之燃料試算功率，對核一廠一號機組之用過核子燃料進行模擬排列，證明現行之規範確實可涵蓋所有燃料之裝載，未來台電實際進行核一乾式貯存系統應用時，可參考本研究之結果作為熱流餘裕之參考。

Taiwan Chinshan Nuclear power plant is ready to be decommissioned, so the spent nuclear fuel stored in its fuel pool is necessary to move into dry storage system as interim storage stage. Tai-power Company has induced the NAC UMS into Taiwan and requested INER to improve UMS into HPS. INER HPS is with fuel basket, TSC, VCC and AOS to store the SNFs and lower the environment dose. Simultaneously, the dry storage system can remove the fuel decay heat through the air channel by natural convection mechanism.
　　This research is focus on the thermal hydraulic phenomenon for the dry storage system. This research analyzed the intact fuel with different thermal loading, fuel pattern and environment condition, causing different temperature distribution, to ensure that the maximum temperature of each component would not be over the limitation. Besides, to consider all possible situations in the future, this research also assesses the damaged fuel and high burn up fuel for all situations. Through collecting the research data about damaged/HBU fuels, this research quantifies their material property inputting to our model to simulate these situations.
　　The results show that not only the intact fuel but the HBU fuel and damaged fuel can store in dry storage system, which can practically apply to Chinshan NPP. Finally, this research combines the real data of SNF in the Chinshan NPP with the simulation results to arrange the fuels into the dry storage system assumingly. This research has demonstrated that the INER HPS is quietly enough to include all the existed SNFs. The Tai-power Company can refer these results in the future while store the fuel practically.

1.原子能委員會，“核能電廠用過燃料池貯存格架改裝安全分析報告審查規範，” 台灣，中華民國79年2月，（79）會核字第1710號。
2. 台灣電力公司，“核一廠用過燃料式貯存設施安全分析報告，”台灣，中華民國97年1月，第六章第三節。
3. 行政院原子能委員會，“游離輻射防護法”，台灣，中華民國91年1月30日，字第09100019000號。
4. U.S.NRC, “FRAPCON-3.4: Integral Assessment,” NUREG/CR-7022, Vol.2, Mach 2011.
5. U.S. Nuclear Regulatory Commission, “Standard Review Plan for Dry Cask Storage Systems,” NUREG-1536, U.S., January 1997.
6. 核能研究所，“池內核子燃料試算功率”，台灣，中華民國91年5月1日。
7. U.S. Nuclear Regulatory Commission, “PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL,” 10 CFR Part 71, U.S., July 2015.
8. JM Cuta, SR Suffield, JA Fort, HE Adkins, “Thermal Performance Sensitivity Studies In Support Of Material Modeling For Extended Storage Of Used Nuclear Fuel.,” PNNL-22646, U.S., September , 2013.
9. U.S. Nuclear Regulatory Commission, “Thermal Analysis of Horizontal Storage Casks for Extended Storage Applications,” NUREG/CR-7191, U.S., December 2014
10. Siemens, “Kuosheng ATRIUM-10 Mechanical Design Evaluation Report and Kuosheng Unit 1 Reload KS1-F13 Atrium-10 Mechanical, Thermal and Neutronic Design Report,” EMF-2491(P) Rev.0, Taiwan, Nov. 2000.
11. U.S. Nuclear Regulatory Commission, “Interim Staff Guidance - 1, Revision 2,” U.S., May 2007.
12. U.S. Nuclear Regulatory Commission, “Criteria for nuclear criticality safety,” 10 CFR 72.124(a), December 02, 2015
13. IAEA, “Nuclear fuel behavior modelling at high burnup and its experimental support,” IAEA-TECDOC-1233, 2001.
14. EPRI-Spent Fuel Transportation Applications— Assessment of Cladding Performance.
15. Pan G, AM Garde, and AR Atwood, in: Proceedings of LWR Fuel Performance Meeting TopFuel 2013, Charlotte, North Carolina, 15-19 September. American Nuclear Society.