|
1.D. Reilly, N. Ensslin, and H. Smith, Jr. , Passive Nondestructive Assay of Nuclear Materials. NUREG/CR-5550, LA-UR-90-732, Los Alamos Scientific Laboratory, 1991. 2.S.T. Hsue, T.W. Crane, W.L. Talbert, and J. C. Lee, Nondestructive Assay Methods for Irradiated Nuclear Fuels, Los Alamos Scientific Laboratory report LA-6923, 1978. 3.S. Muralidhar, R. Tripathi, B.S. Tomar, G.K. Gubbi, S.P. Dange, S. Majumdar, and S.B. Manohar, Nondestructive Assay of the Fissile Content in FBTR Fuel Pins, Nucl. Instr. and Meth. A, vol. 51, pp. 437-443, 2003. 4.D. Davidson, J. Verplancke, P. Vermeulen, H. O. Menlove, H.G. Wagner, B. Brandalise, and M. Stutz, A new high Accuracy Combined Neutron/Gamma Counter for in-glove Box Measurements of PuO2 and MOX Safeguards Samples (OSL-Counter), Proc. 15th ESARDA Symp. on Safeguards and Nucl. Mater. Management, Rome, EUR 15214 EN, pp. 585-588, 1993. 5.L.C-A Bourva, S. Croft, H. Ottmar and D.R. Weaver, MCNP Modelling of a Combined Neutron/Gamma Counter. Nucl Instrum Meth A, vol. 426 pp. 503-517, 1999. 6.Briesmeister, J. F., Ed. MCNP—A general purpose Monte Carlo N-particle transport code, version 4C, LANL Report LA-13709-M (Los Alamos National Laboratory, Los Alamos, NM), 2000. 7.A. L. Thornton, Development of a Portable Neutron Coincidence Counter for Field Measurements of Nuclear Materials Using the Advanced Multiplicity Capabilities of MCNPX 2.5.F and the Neutron Coincidence Point Model, Master’s Thesis, 2007. 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, 2000. 9.J.C. Tait, I. Gauld and A.H. Kerr, Validation of the ORIGEN-S Code for Predicting Radionuclide Inventories in used CANDU Fuel, Journal of Nuclear Materials, vol. 223, pp. 109-121, 1995. 10.J.P. Lestone, J.M. Pecos, J.A. Rennie, J.K. Sprinkle, P. Staples, K.N. Grimm, R.N. Hill, I. Cherradi, N. Islam, J. Koulikov, and Z. Starovich, The passive Nondestructive Assay of the Plutonium Content of Spent-fuel Assemblies from the BN-350 Fast-breeder Reactor in the City of Aqtau, Kazakhstan. Nucl. Instr. and Meth. A, vol. 490, pp. 409-425, 2002. 11.黃盛年,桃園重水式核反應器概要,INER-C0211。 12.李顯謨,桃園重水式核反應器實驗數據與理論值,NER-64-J-T0463,1975。 13.H.C. Hsieh, H.T. Kung, N.N. Hsu, and J.H. Cheng , Experience in TRR Fuel Element Fabrication, Nuclear Science Journal, vol. 13, pp. 53-69, 1976. 14.S.Y. Lee, H.O. Menlove, J.B. Marlow, M.C. Mildder, C.D. Rael, J.B. Wang, and M.C.Yuan, Calibration of the Spent-fuel Pluconium Coincidence Counter at the Taiwn Research Reactor, INMM48, 2007. 15.T. Qian, P. Tonner, N. Keller, and W. Buyers, A Method for Comparing Degradation of Boron Trifluoride and Helium Detectors in Neutron and Gamma Fields, IEEE Transactions on Nuclear Science vol. 45 (3) pp. 636-642, 1998. 16.A.J. Stokes, T.J. Meal, and J. E. Myers, Improved Performance of BF3 Neutron Counters in High Gamma Fluxes, IEEE Transactions on Nuclear Science, vol. 13 (1), pp. 630-635, 1966. 17.D.H. Beddingfield, N.H. Johnson and H.O. Menlove, He-3 Neutron Proportional Counter Performance in High Gamma-ray Dose Environments, Nucl. Instrum. Meth. A, vol. 455 (3) pp. 670-682, 2000. 18.http://140.114.122.100/download.php?filename=94_38a487ec.pdf&dir=news&title=檔案下載 19.C.L. Chen and S.H. Su, The Calibration System of Air Kerma Rate for 137Cs Gamma-ray at 4.23 Meters, INER-5000, 2007. 20.J.E. Swansen, P.R. Collinsworth and M.S. Krick, Shift-Register Coincidence Electronics System For Thermal Neutron Counters, Nuclear Instruments and Methods, vol. 176, pp. 555-565, 1980. 21.J. E. Stewart, S.C. Bourret, M.S. Krick, M.R. Sweet, T.K. Li and A. Gorobets, New Shift Register Electronics for Improved Precision of Neutron Coincidence and Multiplicity Assays of Plutonium and Uranium Mass, LA-UR-99-4927, 1999. 22.SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, ORNL/TM-2005/39, Version 5.1, Vols. I–III, 2006. 23.Denise B. Pelowitz, MCNPXTM User’S Manual, LA-CP-07-1473, 2008. 24.C. J. Chang and J. T. Yang, TRR Spent Fuel Model for the ORIGEN 2 Code, Institute of Nuclear Energy Research, INER-0735, 1987. 25.O. W. Hermann and C. V. Parks, SAS2H: A Coupled One-Dimensional Depletion and Shielding Analysis Module, NUREG/CR-0200, 2000. 26.I.C. Gauld, O.W. Hermann and R.M. Westfall, ORIGEN-S:SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms. Vol. II, Book 1, Sect. F7 ORNL/TM-2005/39, 2006. 27.Michael L. Fensin, John S. Hendricks, Samim Anghaie, The Enhancements and Testing for MCNPX 2.6.0 Depletion Capability, Nuclear Technology, vol. 170 pp. 68-79, 2010. 28.O. W. Hermann and M. D. DeHart, Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel, ORNL/TM-13315, 1998. 29.W. B. Wilson, R. T. Perry, W. S. Charlton, T. A. Parishand E. F. Shores, SOURCES: A Code for Calucluating (a,n), Spontaneous Fission, and Delcayed Neutron Sources and Spectra, Radiation Protection Dosimetry, vol. 115 (14) pp. 117-121, 2005. 30.I. C. Gauld, E. F. Shores, and R. T. Perry, New Neutron Source Algorithms In the ORIGEN-S Code, 12th Biennial RPSD Topical Meeting, April, 2002. 31.W.S. Charlton, R.T. Perry, W.B. Wilson, Benchmarking of the Los Alamos neutron production rate code SOURCES-3A, Nucl. Instrum. Meth. B, vol. 140 pp. 1-8, 1998. 32.John Hendrick, Multiplicity PowerMonte Carlo Sampling of Fission Multiplicity, MC2005, Chattanooga, 2005. 33.Forrest B. Brown, The makxsf Code with Doppler Broadening, LA-UR-06-7002, 2006. 34.Reactor Physics Constants, ANL-5800, 1963. 35.C.C. Tseng, S.C. Cheng, K.Y. Hunag, Analysis of TRR Core Parameters Related to Fuel Irraditation From the Post-Irradiation Gamma Scanning Results, INER-T1150, 1986. 36.C.S. Taso, T.T. Yang, T. Lee and L.F. Lin, Nondestructive Burnup Determination of TRR Testing Fuel Rods FR-01 and S1 by 137Cs Counting Rate and 134Cs/137Cs Activity Ratio from Gamma Spectroscopy, INER-T1251, 1987. 37.C.H. Delegard and A.J. Schmidt, Uranium Metal Reaction Behavior in Water, Sludge, and Grout Matrices, PNNL-17815, 2008. 38.M.S. Krick, Thermal Neutron Multiplicity Counting of Samples with Very low Fission Rates, Los Alamos National Laboratory, LA-UR-97-2649, 1997.
|