本報告主要是嘗試使用SF技術於某研究所核化學實驗室產生之放射性廢棄物，探討其可行性及相關之應用。首先利用移動式超鈾活度量測系統 (ISOCART)量測廢棄物中阿伐核種Am-241與Pu-239等核種及加馬核種Co-60和Cs-137的活度、表面劑量率等。接續利用盒鬚圖法排除樣品中的離群值後，並根據Co-60和Cs-137活度比值進行分群動作，共分成8群。再將前述各群進行比例因數計算。
比例因數計算方法國際間有多種作法，本報告最後採用與EPRI建議之對數平均法作為計算比例因數之方法；從計算結果得知，難測核種Pu-239對應之關鍵核種選擇Co-60或Cs-137均可，其理論計算所得之比例因數和實際真正之比例因數誤差值在30%以內者約占6成以上，具參考價值；另難測核種Am-241對應之關鍵核種選擇則不應是Co-60或Cs-137。
最後將算得之SF值並將其應用於TRU廢棄物接收流程中，作為接收標準之參考依據，此舉將使放射性廢棄物之營運管理更臻完善。本文案例中並成功篩選出8桶廢棄物桶疑似超過TRU廢棄物接收標準需退回重裝。

This report mainly attempts to use SF technology in the radioactive waste generated from the laboratory, to explore its feasibility and related applications. First, using ISOCART to measure the activity and the surface dose rate of Am-241, Pu-239, Co-60, and Cs-137 in the waste. Then proceed to exclude outliers in the sample by using Box plot, and according to the activity ratios of Co-60 and Cs-137, they were divided into 8 groups. Finally, calculate the scale factor for each group.
There are many methods for calculating the scaling factor. In this report, the logarithmic average method recommended by EPRI is used as the method for calculating the scaling factor. According to the calculation results, the key nucleus corresponding to Pu-239 can be selected as Co-60 or Cs-137.；Conversely, the key nucleus selection for the nuclear Am-241 should not be Co-60 or Cs-137. And finally we apply the calculated SF value to the TRU waste acceptance process. This will further improve the management of radioactive waste. In this case, we successfully screened out 8 barrels of waste that exceeded the TRU waste acceptance criteria and needed to be returned for reloading.

1. Andrews A (2006) Radioactive waste streams: waste classification for disposal, CRS Report for Congress, Order Code RL32163, December 13.
2. Kim SI, Lee KJ (2006) assessment of the activation activity of the fuel assembly from transmutation reactor PEACER, WM06 Conference, Feb 26 to Mar 2, Tucson.
3. Lowenthal MD (1997) Radioactive-waste classification in the United States: history and current predicaments, Lawrence Livermore National Laboratory, UCRL-CR-128127, S/C # B332804.
4. U.S. Code of Federal Regulations, Title 10, Part 61(10 C.F.R. 61).
5. 放射性物料管理法，原子能委員會，91.12.25 公布。
6. International Organization for Standardization. ISO 21238, “Nuclear energy - Nuclear fuel technology -Scaling factor method to determine the radioactivity of low- and intermediate-level radioactive waste packages generated at nuclear power plants,” Geneva, 2007.
7. IAEA. Tech. Report No. NW-T-1.18, “Determination and use of scaling factors for waste characterization in nuclear power plants,” Vienna, 2009
8. ISOTOPIC-32 Software Version 4.1-User’s Manual, 2008.AMETEK/ORTEC.
9. ISOCS Calibration Software-User’s Manual, 2002. Canberra Industries, Inc.,Meriden.
10. Yuan, M.C., Yeh, C.H., Wang, J.J., Chen, I.J., Wang, C.F., 2009. The calibration and evaluation of a radioactive waste drum counting system. Appl. Radiat. Isot. 67, 931-934.
11. Knoll, G.F., 2010, Radiation Detection and Measurement, 4th ed., John Wiley& Sons, Inc., USA.
12. ISO/TAG4/WG3, “Guide to the Expression of Uncertainty in Measurement”,1995.
13. ANSI N42.14-1991, “American National Standard for Calibration and Use of Germanium Spectrometers for the Measurement of Gamma-Ray Emission Rates of Radionuclides”.
14. Richard, B. Firestone, “Table of Isotopes”, 8th ed., John Wiley & Sons Inc.
15. 譚克平，極端值判斷方法簡介，台東大學教育學報第十九卷第一期，131-150,2008.
16. EPRI, “Utility use of constant scaling factors”, EPRI-TR-109448, California ,USA ,1999.
17. A.Raymond 等人, “Inventory and characterization of important radionuclides for the safety of storage and disposal.-correlation with key radionuclides in typical waste streams”, Journal of Radioanalytical and Nuclear Chemistry,Articles,193(2),p377-390,1995.
18. 周子鑫，〝赴美國橡樹嶺國家實驗室〞核能研究所國外公差報告，2015。
19. TRUPACT-II Safety Analysis Report for Packaging (SARP) in Section 9.4 of Appendix 1.3.7.
20. TRANSURANIC WASTE ACCEPTANCE CRITERIA for THE WASTE ISOLATION PILOT PLANT，DOE-WIPP-02-3122，rev7.4，2013.04.22.