gamma Radiation Spectrum Analysis of Irradiated Fuel at Different Cooling Times and the Best Fuel Burnup and Power Monitors in Tehran Research Reactor

Document Type : Full length research Paper

Authors

1 shiraz university

2 AEOI

Abstract

One of the non-destructive methods in evaluating the characteristics of irradiated fuels in any reactor is the gamma radiation spectroscopy. A qualitative and quantitative analysis of the spectrum of an irradiated fuel and the estimation of some fissile products as a fuel burnup and the power peaking factor monitors in a fuel assembly is necessary. On the other hand, some experimental constraints, including the resolution of the detector energy, prevent the detection of some fission products and hide certain information in the spectrum. Therefore, in this study, the content of fissile fragments of Tehran Research Reactor fuel at different cooling times (3, 30, 120, 360 and 720 days) was evaluated with the ORIGEN2.1 computational code and the spectrum of fission products by Monte Carlo code MCNPX2.7 have been simulated. Then fission products that can be considered as a good monitors of fuel burnup have been analyzed.

Keywords


[1]   B.B. Bevard, Review of Information for Spent Nuclear Fuel Burnup Confirmation, US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, (2009).
[2]   C. Leuthrot, A. Brissaud, A. Harrer, IAEA Tecdoc-709, IAEA, Vienna (1992).
[3]   L.A.A. Terremoto, C.A. Zeituni, J.A. Perrotta, JER. Da. Silva, Gamma-Ray Spectroscopy on Irradiated Mtr Fuel Elements, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 450 (2000) 495-514.
[4]   M.V. Mora, A.G. Padilla, J.L.C. Palomino, L.A.A. Terremoto, Nondestructive burnup measurements by gamma-ray spectroscopy on spent fuel elements of the RP-10 research reactor, Progress in Nuclear Energy, 53 (2011) 344-353.
[5]   T. Akyurek, LP. Tucker, Sh. Usman, Review and Characterization of Best Candidate Isotopes for Burnup Analysis and Monitoring of Irradiated Fuel, Annals of Nuclear Energy, 69 (2014) 278-91.
[6]   S. Vaccaro, S. J. Tobin, A. Favalli, B. Grogan, P. Jansson, H. Liljenfeldt, V. Mozin, J. Hu, P. Schwalbach, A. Sjöland, PWR and BWR Spent Fuel Assembly Gamma Spectra Measurements, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 833 (2016) 208-25.
[7]   A.G. Croff, User's Manual for the Origen2 Computer Code,  Oak Ridge National Lab, TN (USA), (1980).
[8]   L.S. Waters, Mcnpx User’s Manual, Los Alamos, (2002).
[9]   A. Lashkari, H. Khalafi, S.M. Mirvakili, S. Forughi, Neutronic Analysis for Tehran Research Reactor Mixed-Core, Progress in Nuclear Energy, 60 (2012) 31-37.
[10]   AEOI Atomic Energy Organization of Iran, Safety Analysis Report for the Tehran Research Reactor (LEU), Tehran-Iran, (2001).
[11]   J. Navarro, TA. Ring, DW Nigg, A Feasibility and Optimization Study to Design a Nondestructive Atr Fuel Permanent Scanning System to Determine Fuel Burnup, Nuclear Data Sheets, 118 (2014) 571-74.
[12]   M. Svadlenkova, L. Heraltova, V. Juricek, M. Kostal, E. Novak, Gamma Spectrometry of Short Living Fission Products in Fuel Pins, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 739 (2014) 55-62.
[13]   T. Akyurek, L.P. Tucker, S. Usman, Review and Characterization of Best Candidate Isotopes for Burnup Analysis and Monitoring of Irradiated Fuel, Annals of Nuclear Energy, 69 (2014) 278-91.
[14]   E. Browne, J.M Dairiki, R.E. Doebler, Table of Isotopes, National Standard Reference Data System (1978).