‎Assessment of shielding performance of nitrile butadiene rubber through simulation and experiments at MNSR beam line

Gholamzadeh, Zohreh; Ebrahimzadeh, Reza; Choopan Dastjerdi, Mohammad Hossein; Mokhtari, Javad

doi:10.22034/rpe.2024.420403.1167

Document Type : Research Article

Authors

Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, Atomic Energy Organization of Iran, Iran

https://doi.org/10.22034/rpe.2024.420403.1167

Abstract

New nitrile butadiene rubber (NBR) materials are being considered to use for neutron shielding especially for the positions which needs a flexible neutron shield. Such light, low-cost, and suitable material could be used for sealing of the gaps or even for shielding of low radiation environments. In the present work, experimental investigation of NBR shielding performance of neutrons and gamma rays was proposed using the beam line of the Isfahan Miniature Neutron Source Reactor . MCNPX code was used to simulate the 30 kW research reactor beam line. Six NBR sheet with 2 cm thickness were used at the outlet of the beam line respectively to measure its neutron shielding as well as gamma shielding power on thickness. The experiment situations were modeled using the computational code. The obtained results showed the flexible and cheap material could be used as a good neutron shield while it acts as a very weak shield for gamma rays too. Also there is good conformity between simulation and experimental data with maximum 37% relative discrepancy.

Highlights

NBR is used as one of the most powerful flexible neutron shields.
Research reactors could use flexible neutron shield around non-uniform surfaces.
Neutron dose rate decreases about to its half value using the NBR with suitable thickness.
Measurements help to estimate the NBR behavior before its installation.

Keywords

References

Aziz, O., Salama, E., E. El-Nashar, D., et al. (2023). Development of Sustainable Radiation-Shielding Blend Using Natural Rubber/NBR, and Bismuth Filler. Sustainability, 15(12):9679.

Ceresana (2018). Ceresana. Synthetic Rubber-Study: Market, Analysis-Ceresana. www.ceresana.com. Archived from the original on 4 November 2017. Retrieved 7 May 2018. Ceresana.

Chengzhan, G. and Yongchun, G. (1994). Safety analysis report for miniature neutron source reactor (MNSR). China Institute of Atomic Energy Report RPT4-S-430-SIAE/SA, RC, FL, RP.

Dastjerdi, M. C., Mokhtari, J., Asgari, A., et al. (2019). A neutron radiography beamline relying on the Isfahan Miniature Neutron Source Reactor. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 928:20–25.

Dastjerdi, M. C., Mokhtari, J., and Toghyani, M. (2023a). Design, construction, and characterization of a Prompt Gamma Neutron Activation Analysis (PGNAA) system at Isfahan MNSR. Nuclear Engineering and Technology, 55(12):4329–4334.

Dastjerdi, M. C., Mokhtari, J., Toghyani, M., et al. (2023b). Feasibility study on PGNAA experiments using a prototype neutron beam at Isfahan MNSR. Journal of Instrumentation, 18(07):P07031.

Ghasemi, Z., Hassanvand, M., Dastjerdi, M. C., et al. (2023). Design of a radiation shield for an HPGE detector for a reactor-based PGNAA facility. Radiation Physics and Chemistry, 210:111045.

Güngör, A., Akbay,˙I., Ya¸ sar, D., andÖzdemir, T. (2018). Flexible X/Gamma ray shielding composite material of EPDM rubber with bismuth trioxide: mechanical, thermal investigations and attenuation tests. Progress in Nuclear Energy, 106:262–269.

Hegazi, E. M. (2018). Study of shielding properties for NBR rubber/nano silica composites against gamma radiation. IOSR Journal of Polymer and Textile Engineering.

Jumpee, C. and Wongsawaeng, D. (2015). Innovative neutron shielding materials composed of natural rubber-styrene butadiene rubber blends, boron oxide and iron (III) oxide. In Journal of Physics: Conference Series, volume 611, page 012019. IOP Publishing.

Koˇst’ál, M., Losa, E., Schulc, M., et al. (2021). Testing of various neutron filters in reference neutron field in LR-0 reactor for nuclear data validation and verification. Applied Radiation and Isotopes, 169:109566.

Mokhtari, J. and Dastjerdi, M. C. (2023). Development and characterization of a large thermal neutron beam for neutron radiography at Isfahan MNSR. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1051:168209.

Onjun, O., Laothong, N., Picha, R., et al. (2014). Natural rubber blocks as thermal neutron shields. Progress in Nuclear Science and Technology, 4:631–634.

Pelowitz, D. (2008). MCNPX user’s manual report LA-CP-07-1473. Los Alamos National Laboratory.

Rahmati, E., Barough, M. S., Dastjerdi, M. C., et al. (2023). Design of an out-of-tank neutron beam line for prompt gamma neutron activation analysis at low-power Miniature Neutron Source Reactor. Journal of Instrumentation, 18(09):P09036.

Sukegawa, A. M. and Anayama, Y. (2014). Flexible heat-resistant neutron and gamma-ray shielding resins. Progress in Nuclear Science and Technology, 4:627–630.

Sumirat, I., Sulistioso, G., Mahendra, A., et al. (2020). Analysis of neutron absorption from NBR rubber type without and with Gd and B4C fillers. In Journal of Physics: Conference Series, volume 1436, page 012083. IOP Publishing.

Threadingham, D., Obrecht, W., Lambert, J.-P., et al. (2000). Rubber, 3. synthetic. Ullmann’s Encyclopedia of Industrial Chemistry.

Vatani, M., Hassanvand, M., Mokhtari, J., et al. (2023). Design of an in-tank thermal neutron beam for PGNAA application at Isfahan MNSR. Nuclear Engineering and Design, 412:112451.

Radiation Physics and Engineering

‎Assessment of shielding performance of nitrile butadiene rubber through simulation and experiments at MNSR beam line

References

References

Volume 5, Issue 2
April 2024
Pages 43-50

‎Assessment of shielding performance of nitrile butadiene rubber through simulation and experiments at MNSR beam line

References

References

Volume 5, Issue 2April 2024Pages 43-50

Volume 5, Issue 2
April 2024
Pages 43-50