隨著全球暖化的議題發酵，核能發電成為能源重要的解決方案之一，使用核能最為人關注的是在於核廢料的處理，尤其是具有高度放射性的用過燃料，本篇論文主要討論用過燃料射源項與燃料元件參數之間的關係，並且對於放射性核種做定量分析，最後討論 THOR 與 BWR 用過燃料在相同燃耗下射源項與放射性核種的比較。

本篇論文主要使用 SCALE 系統內的 SAS2H 控制模組，計算用過燃料的射源項與放射性核種。針對核一廠 GE BWR 8x8-1 燃料元件，做燃料元件參數調整，定訂出各射源項隨參數變化的次方係數。結果顯示燃耗與燃料密度的改變會造成次方係數為正值的影響；另外燃料濃縮度與緩和劑密度的變動造成次方係數為負值的影響。在 GE BWR 8x8-1 用過燃料核種定量分析中發現長半衰期的放射性核種大於國內管制的豁免活度濃度，即使錒系核種完全移除，用過燃料仍須送往深層地質處置場做最終處置。另外可做為標準中子射源或阿伐射源的 Cf-252 與 Am-241 因量少而不具提煉的經濟效益，而貝他與加馬射源 Sr-90 、 Y-90 、 與 Cs-137 在標準燃耗條件下的活度約為一萬多居里。最後根據模擬計算結果發現 Cs-134/Cs-137 的活度比是相當良好的燃耗指標。

THOR 與 BWR 用過燃料在相同燃耗條件下，造成每公噸鈾所產生的加馬射源相近，此外因為燃料濃縮度以及中子通率的不同，使得每公噸鈾產生的中子射源前者較後者約小萬倍左右。

1. M. J. Bell, ORIGEN-The ORNL Isotope Generation and Depletion Code, ORNL-4628 (CCC-217), Union Carbide Corp., Nucl. Div., Oak Ridge Natl. Lab., May 1973
2. O. W. Hermann and C. V. Parks, SAS2H： A Coupled One-Dimensional Depletion and Shielding Analysis Module, Vol. 1, Sect. S2, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD- 2/R6), Oak Ridge Natl. Lab., May 2000.
3. O.W. Hermann and R. M. Westfall, ORIGEN-S： Scale System Module to Calculate Fuel Depletion, and Associated Radiation Source Terms, Vol. 2, Sect. F7, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/V2/R6), Oak Ridge Natl. Lab., March 2000.
4. N. M. Greene, BONAMI： Resonance Self-shielding by the Bondarenko Method, Vol. 2, Sect. F1, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/V2/R6), Oak Ridge Natl. Lab., March 2000.
5. N. M. Greene, L. M. Petrie and R. M. Westfall, NITAWL-II： SCALE System Module for Performing Resonance Shielding and Working Library Production, Vol. 2, Sect. F2, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/V2/R6), Oak Ridge Natl. Lab., March 2000.
6. N. M. Greene and L. M. Petrie, XSDRNPM： A One-Dimensional Discrete-ordinates Code for Transport Analysis, Vol. 2, Sect. F3, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/V2/R6), Oak Ridge Natl. Lab., March 2000.
7. O. W. Hermann, COUPLE：SCALE System Module to Process Problem-Dependent Cross Sections and Neutron Spectral Data For ORIGEN-S Analyses, Vol. 2, Sect. F6, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/V2/R6), Oak Ridge Natl. Lab., March 2000.
8. O. W. Hermann, S. M. Bowman, M. C. Brady, and C. V. Parks, Validation of the SCALE System for PWR Spent Fuel Isotopic Composition Analyses, ORNL/TM-12667, Oak Ridge Natl. Lab., March 1995.
9. Jinn-Jer Peir, An Iterative Approach for TRIGA Fuel Burnup Determination Using Nondestructive Gamma-Ray Spectrometry, National Tsing-Hua University, 1998
10. B. L. Broadhead, Guidelines for Preparation of Shielding Evaluations for Transport and Storage Packages, ORNL/TM-2002/31, UT-Battelle, LLC, Oak Ridge Natl. Lab., October 2002.
11. http://wapp4.taipower.com.tw/nsis/option0-1.asp
12. http://www.ornl.gov/sci/rrd/pages/hfir.html
13. John R. Lamarsh, Anthony J. Baratta, Introduction to Nuclear Engineering, 3rd ed., Prentice Hall, 2001
14. J. K. Bair and J. Gomez del Campo, Neutron Yields from Alpha-Particle Bombardment, Nucl. Sci. Eng. ; Vol/Issue: 71:1, Oak Ridge Natl. Lab., July 1979.
15. Y. F. Chen, Theoretical Investigation of Minor Actinides Reduction in Fully Closed Fuel Cycle, Master thesis, National Tsing-Hua Uni., August 2006.
16. BWR Gamma and Neutron Source Term, EA790-4002, NAC International, September 1997