A. G. Crofft, A User’s Manual for the ORIGEN 2.1 Computer Code, Rep. ORNL/TM-7175Oak Ridge National Laboratory, (July 1980).
INTERNATIONAL ATOMIC ENERGY AGENCY, Research Reactor Core Conversion Guidebook, IAEA-TECDOC-643, Vol. 2, IAEA, Vienna (1992).
Hyedong Jeong & Soon Heung Chang, Estimation of the Fission Products, Actinides and Tritium of HTR-10, Korea Advanced Institute of Science and Technology, (Sep 2009).
Sana Ullahb, Saeed Ehsan Awana, Source Term Evaluation for the upgraded LEU Pakistan Research Reactor-1 under severe accidents, Nuclear Engineering and Design 240 (2010), 3740–3750, (Aug 2010).
Wm. J. Garland, Decay Heat Estimates for MNR, McMaster Nuclear Reactor-McMaster University Hamilton, Ontario, (Feb 1999).
Josip Vuković, Davor Grgić, Damir Konjarek, ORIGEN2.1 Cycle Specific Calculation of Krško Nuclear Power Plant Decay Heat and Core Inventory, the 8th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids Dubrovnik, Croatia, (May 2010).
T. R. R. Amendment to the Safety Analysis Report, Prov. de Rio Negro, Argent., (Sep 1989).
M. Shams, Evaluation of source term in accident of research reactors and its biological impacts, Mechanical Engineering Department, Sharif University of Technology (Shahrivar 1369).
N. Tehrani, Source term calculation in TRR (part 1: Equilibrium core), AEOI, Reactors and Accelerators Research School (Khordad 1390).
Atomic Energy Organization of Iran, Safety Analysis Report for Tehran Research Reactor, (January 2009).
N. Tehrani, Source term calculation in TRR (part 2: core # 57-C), AEOI, Reactors & Accelerators Research School (Mehr 1390).
AEOI, Tehran Research Reactor Logbooks (1389).
International Atomic Energy Agency, Safety Reports Series No. 53, Derivation of the Source Term and Analysis of the Radiological Consequences of Research Reactor Accidents, VIENNA (2008).