Radiation Physics and Engineering
A peer-reviewed journal published by K. N. Toosi University of Technology

Benchmark MCNP computer code simulation results against experimental data of neutron flux and spectrum from neutron imaging system of Tehran research reactor

Document Type : Research Article

Authors

Majid Zamani
Mohsen Shayesteh

Physics Department, Imam Hossein University, P. O. Box 16575-347, Tehran, Iran

https://doi.org/10.22034/rpe.2023.406935.1152
Abstract
Using the experimental data in nuclear computing to verify the calculation methods and tools based on numerical and statistical methods has many benefits such as illustrating the quality, ensuring the capabilities, and computer codes validating. Simulation by computer tools is also applicable in the safety analysis of research reactors. In this research, the computer tool (MCNPX 2.7.0: 2011) was verified against the experimental data of neutron flux and spectrum on the sample position of the Tehran Research Reactor (TRR) neutron imaging system by the neutron activation method. To determine the benchmark specifications, the simulation of the system was done at the first step by considering a well-defined facility geometric, material specification and reactor core configuration, fuel elements, and radiation facility (beam tubes and collimator, reactor core, and neutron imaging components). Then the flux and neutron spectrum at the sample position were calculated. In the second step, a set of In (bare and covered by cd) and Au foils and a set of Au, Ni, Ti, and Zr, were placed and exposed almost in front of the reactor E beam tube. The neutron energy spectrum was unfolded by calculating the saturation activity of each foil by SAND-II code, and the neutron flux was calculated. A comparison of the results obtained in two steps shows a relatively good and acceptable agreement (Max. 30% deviation) between the flux and the shape of the flux profile obtained from calculations and experimental data.

Highlights

  • Irradiation of samples by monochromatic neutron beam of E-beam tube.
  • Using the neutron activation method to determine the neutron flux.
  • Investigating the neutron imaging system of the Tehran Research Reactor (TRR).
  • Unfolding the neutron energy spectrum.
  • Benchmark study to validate the calculation tool against experimental data.

Keywords

Benchmarking
MCNPX
Neutron flux
Spectrum
Neutron imaging
Tehran Research Reactor
Chadwick, M., Obloˇ zinsk` y, P., Herman, M., et al. (2006). ENDF/B-VII. 0: next generation evaluated nuclear data library for nuclear science and technology. Nuclear Data Sheets, 107(12):2931–3060.
Dastjerdi, M. C., Khalafi, H., Kasesaz, Y., et al. (2016). Design, construction and characterization of a new neutron beam for neutron radiography at the Tehran Research Reactor. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 818:1–8.
Dastjerdi, M. C., Movafeghi, A., Khalafi, H., et al. (2017). The quality assessment of radial and tangential neutron radiography beamlines of TRR. Journal of Instrumentation, 12(07):P07008.
Dastjerdi, M. H. C. and Khalafi, H. (2015). Design of a thermal neutron beam for a new neutron imaging facility at Tehran research reactor. Physics Procedia, 69:92-95.
Dehkordi, A., Habashi, S., and Rahimian, H. (2019). Neutronic and safety study of the dry channel in the Tehran Research Reactor core. Proceeding of 26th Iran National Nuclear Conference.
Di Tigliole, A. B., Cammi, A., Chiesa, D., et al. (2014). TRIGA reactor absolute neutron flux measurement using activated isotopes. Progress in Nuclear Energy, 70:249–255.
El Bakkari, B., El Bardouni, T., Merroun, O., et al. (2009). Development of an MCNP-tally based burnup code and validation through PWR benchmark exercises. Annals of Nuclear Energy, 36(5):626–633.
Heydarzade, A., Kasesaz, Y., and Mohammadi, S. (2018). Coupling the SAND-II and MCNPX codes for neutron spectrum unfolding. Journal of Instrumentation, 13(08):P08010.
IAEA (2015). Research Reactor Benchmarking Database: Facility Specification and Experimental Data, Technical Reports Series No. 480. International Atomic Energy Agency. IAEA (2022).
Benchmarks of Fuel Burnup and Material Activation Computational Tools Against Experimental Data for Research Reactors, Results of a Coordinated Research Project, TECDOC-1992. International Atomic Energy Agency.
Iwamoto, Y., Sato, T., Hashimoto, S., et al. (2017). Benchmark study of the recent version of the PHITS code. Journal of Nuclear Science and Technology, 54(5):617 635.
Kasesaz, Y., Rokrok, B., and C Dastjerdi, H. (2020). Radiation Safety Assessment of the New Neutron Radiography System at Tehran Research Reactor. Radiation Safety and Measurement, 9(4):251–256.
Olsher, R. H., Hsu, H.-H., and Harvey, W. F. (1993). Benchmarking the MCNP Monte Carlo code with a photon sky shine experiment. Nuclear Science and Engineering, 114(3):219–227.
Pelowitz, D. B. et al. (2005). MCNPX user’s manual version 2.5. 0. Los Alamos National Laboratory, 76:473.
Rokrok, B., Choopan Dastjerdi, M. H., and Movafeghi, A. (2021). Design and construction of the neutron radiography facility for Tehran Research Reactor with real-time digital imaging capability. NDT Technology, 2(7):24–32.
SNL-SANDII (1996). Neutron Flux Spectra from Multiple Foil Activation Analysis. Sandia national laboratories, Albuquerque, New Mexico, USA.
Tiyapun, K., Chimtin, M., Munsorn, S., et al. (2015). Validation of the MCNP computational model for neutron flux distribution with the neutron activation analysis measurement. In Journal of Physics: Conference Series, volume 611, page 012007. IOP Publishing.
Zamani, M. and Shayesteh, M. (2022). Updated Calculation of Neutron and Gamma flux and Spectrum in E Beam Tube of Tehran Research Reactor, Used in Digital Neutron Imaging System. Proceeding of 29th Iran National Nuclear Conference.
Radiation Physics and Engineering
Volume 5, Issue 1
Winter 2024
Pages 11-19

  • Receive Date 13 July 2023
  • Revise Date 31 July 2023
  • Accept Date 16 August 2023

Home

Submit Manuscript

Reviewers

Contact Us