核能幾為現今人類不可或缺的能源，而使用核能發電後，勢必會產生用過核燃料，這些用過核燃料因為會持續發出衰變熱及放射線，它們的貯存一直是一個很麻煩的問題，沒有足夠的空間將造成核電廠無法繼續運轉，不安全的貯存則可能造成危險甚至是燃料毀損。乾式貯存系統已經被證實能有效的解決用過燃料的屯貯問題。目前我國雖然已自美國引進系統之雛型，但不論是建構適合臺灣使用的系統或是使用前的審核工作，都必須進行詳細的熱流模擬分析，對於這項需求，核能研究所適時引進商用CFD軟體Fluent來輔助分析工作的實行。目前的分析流程已趨於完善，並且在此套流程下所進行的分析工作在精確度上確實達到建構系統所需要的水準，但部份的流程卻為分析人員所垢病；例如過多重複性且無必要的計算工作，以及Fluent資料庫更新上的不便。本研究擬利用Visual Basic軟體撰寫自訂軟體ADSS，從以上問題點切入，將乾貯系統熱流分析中常需簡化之燃料組件與燃料提籃之均質化模式以及功率分佈預先模組化，並與Fluent資料庫作聯結，配合視窗化的操作介面，能使熱流模擬分析工作能更有效率。在此軟體完成後本研究也利用其特性，來確認用過核子燃料的結構改變是否會對乾式貯存系統的安全分析有重大的影響。

For modern people almost can’t live without Nuclear energy, we must face some problems which are made by Nuclear power. In the processes of nuclear power plants operation, spent fuel is definitely produced. The storage of the spent fuel is always a big problem. Insufficient of storage space can let power plants stop operate and unsafe storage can create nuclear disaster. Spent fuel dry storage system can do some help on that. We do introduce a system module from USA, but it’s not a system that suit for Taiwan. To design and construct a suitable system for Taiwan, we need to do CFD simulations. INER do these jobs with some helps from FLUENT. FLUENT is a commercial CFD program with strong ability. With the helping of FLUENT, INER get the accurate result of simulations. But some steps of simulations have disadvantages, like the iterations and hard on database renewing for FLUENT. With Visual Basic, we produce a new program, ADSS, to solve above problems. This program contains modulized calculation models for fuel assembly, homogenization model for fuel bundles and power distribution. It can also connect with FLUENT and with windows operation interface. This program can make the simulation processes be more effective. With ADSS’ characteristic, we also check if rod bowing could be a trouble on CFD simulations.

1. U.S. NRC, “Backgrounder on the Three Mile Island Accident”, 2008.
2. EPRI (Electric Power Research Institute), “Evaluation of the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Using Total System Performance Assessment”, Technical Report 1003031, Palo Alto, California, 2002.
3. OECD Nuclear Energy Agency. “Management of recyclable fissile and fertile materials” OECD Publishing, France, 2011, p. 34
4. NAC Inc., “NAC-UMS Universal MPC System Final Safety Analysis Report,” NAC INTERNALTIONAL, R-208624, Rev. 8A, Feb. 2009.
5. 台灣電力公司， “核一廠用過核子燃料乾式貯存設施安全分析報告，”第6 章第3 節 熱流分析。
6. 楊宗佑，“核一廠乾式貯存設施密封鋼筒穩態熱傳分析計算書＂ISFSI-04-CAL -04-06002-03。
7. Pacific Northwest Laboratory and Idaho National Engineering Laboratory, “Performance Testing and Analyses of the VSC-17 Ventilated Concrete Cask”, EPRI TR-100305, Final Report, May 1992
8. Yung-Shin Tseng, Jong-Rong Wang, Yi-Hsiang Cheng and Chunkuan Shih, “The Cooling Design Investigation for a High Capability Dry-Storage System through CFD simulation,” ANS 2008 Winter Conference, Fuel Cycle and Waste Management: General—III, page 213-215
9. Yung-Shin Tseng, Jong-Rong Wang, Yi-Hsiang Cheng and Chunkuan Shih, “Validation Study of FLUENT for the Application of Dry-Storage System Thermal Analysis,” ICAPP 09 Tokyo, Japan, May10-14, 2009 Paper 9051.
10. U.S. NRC, “Packaging and Transportation of Radioactive Material,” 10 CFR Part 71, April 1996.
11. U.S. NRC, “Standard Review Plan for Dry Cask Storage Systems,”NUREG-1536, January 1997.．
12. U.S. NRC, “Cladding Considerations Transportation and Storage of Spent Fuel,” ISG-11, Rev. 3.
13. A. Billerey, “Evolution of Fuel Rod Support Under Irradiation Impact on the Mechanical Behavior of Fuel Assemblies”, IAEA-TECDOC-1454, November, 2004 page 101-111
14. ANSYS Inc., FLUENT 6.2 UDF Manual, 2005.
15. 張自豪, “熔鹽式反應器-速度分佈器設計模擬研究”, 國立清華大學,碩士論文,民國九十九年
16. 楊凱鈞, “高容量乾式貯存系統之等效熱阻與靈敏度分析以及熱傳改善研究”, 國立清華大學, 碩士論文, 民國九十九年
17. 張庭碩, “利用FLUENT 進行高容量乾式貯存系統傳送護箱暫態熱流分析’, 國立清華大學, 碩士論文, 民國九十九年
18. Wei-Keng Lin, Jong-Rong Wang, Yung-Shin Tseng, “Development of Software for Evaluations of Keff in Spent Fuel Dry Storage System”, ANS 2010 Winter Meeting, November, 2010, paper 2309
19. Wei-Keng Lin, Chun-Khan Shih, Jong-Rong Wang, Yung-Shin Tseng, Jui-En Chang, “Mathematical Model for Design of Spent Fuel Dry Storage System”, ANS 2011 Winter Meeting, November, 2011, paper 4553
20. 林唯耕、施純寬、王仲容、曾永信、張睿恩、吳亮東, “核燃料束和燃料套管之等效熱傳性質及其VB操作介面應用程式之建立”,中國機械工程學會第二十七屆全國學術研討會論文集, 2010, AA12-003
21. 林唯耕、施純寬、王仲容、曾永信、張睿恩, “以 VB 操作介面應用程式計算核燃料束和燃料套管等效熱傳性質之研究”, 中國機械工程學會第二十八屆全國學術研討會論文集, 2011, AA4-008