1 |
M. Wallenius, K. Mayer, I. Ray, Nuclear forensic investigations: two case studies, Forensic Sci. Int. 156 (2006) 55-62.
DOI
|
2 |
A. Glaser, T. Bielefeld, Nuclear Forensics: Capabilities, Limits, and the CSI Effect, Presentation Material at the Conference on Science and Global Security, Massachusetts Institute of Technology, Cambridge, MA, July 24, 2008.
|
3 |
HELIOS Methods, Studsvik Scandpower, 1998.
|
4 |
M. Edenius, B.H. Forssen, H. Haeggblom, CASMO-3 A Fuel Assembly Burnup Program Methodology, STUDSVIK/NFA-89/2.
|
5 |
K.S. Kim, KARMA 1.2 Code Methodology Manual, S06NX08-A-2-TR-07 Rev.01, Korea Atomic Energy Research Institute, 2011.
|
6 |
J.Y. Cho, J.C. Lee, K.H. Lee, S.Y. Park, H.J. Park, H.Y. Kim, K.Y. Kim, H.J. Jung, J.S. Song, S.G. Zee, C.K. Jo, H.C. Lee, DeCART v.1.2 User's Manual, KAERI/TR-3438/2007, Korea Atomic Energy Research Institute, 2007.
|
7 |
S. Ludwig, ORIGEN: The ORNL Isotope Generation and Depletion Code, CCC-0371/17, Oak Ridge National Laboratory, 2002.
|
8 |
D.Y. Kim, S.G. Hong, Development of Inverse Estimation Program of Burnup Histories for Nuclear Spent Fuel Based on ORIGEN-S, Transactions of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Korea, October 30-31, 2014.
|
9 |
S.G. Hong, et al., Development and Validation of A Code System and Extended Library for Burnup History Estimation of Spent Fuel Based on the Measurement of Environmental Samples, KINAC/CR-003/2015 (B4-8110), Korea Institute of Nuclear Nonproliferation and Control, 2015.
|
10 |
O.W. Hermann, R.M. Westfall, ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, ORNL/NUREG/CSD-2/V2/R6, Oak Ridge National Laboratory, 1998.
|
11 |
OECD/NEA, Post Irradiation Examination for Examination for Spent Fuel Sample (Mihama-3). Available from: http://www.oecd-nea.org/sfcompo/Ver.2/Eng/Mihama-3/index.html'
|
12 |
RISCC, SCALE 6.1: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design; Includes ORIGEN, CCC-785, Radiation Safety Information Computational Center.
|
13 |
S.E. Jensen, E. Nonbel, Description of the Magnox Type of Gas Cooled Reactor (MAGNOX), Rise National Laboratory, 1999.
|
14 |
OECD/NEA, Post Irradiation Examination for Examination for Spent Fuel Sample (Cooper). Available from: http://www.oecd-nea.org/sfcompo/Ver.2/Eng/Cooper/index.html.
|
15 |
M.R. Scott, Nuclear Forensics: Attributing the Source of Spent Fuel Used in an RDD Event, M.S. thesis, Texas A&M University, 2005.
|