Performance estimation of lead-free dual-layered shielding in dismantling of steam generator: A Monte-Carlo simulation study

Decommissioning is the final stage of a nuclear reactor. In preparing the decommissioning plan, one of the important elements that need to be considered is safety assessment. During decommissioning, there are many complex tasks to be done where the radiological and non-radiological hazards arise and can significantly affect not only the workers but also the general public and the environment. Indonesia has no experience with nuclear reactor decommissioning, so it is necessary to study various experiences of decommissioning activities in the world. This study proposes a framework to implement the safety assessment on the decommissioning of the TRIGA 2000 research reactor. The framework was developed on desk-based research and analysis. The proposed framework involves the facility and decommissioning activities, hazard identification, hazard analysis, hazard evaluation, hazard or risk control, and independent review.

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“…Some materials can reduce the dose rate. The types of shielding depend on the type of radiation and its energy levels [34]. -Source reduction.…”

Section: Evaluation Of Results and Identification Of Safety Measuresmentioning

confidence: 99%

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

Tyas

Deswandri²,

Intaningrum³

et al. 2022

Tri Dasa Mega

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“…Performance of various materials for Pb-free shielding were compared with that of Pb shielding. For Pb-free shielding shows excellent radiation shielding rate and deduce the bremsstrahlung radiation 30 . The composite polymer-based for shield by using natural rubber filled with Bi 2 O 3 and more complex filler using acetates/ carboxylates/ BiF3/ ThF 4 / metal/ fluorides shows HVL 0.2 cm −1 for energy 50 keV and HVL 0.21 cm −1 for energy 45 keV, respectively 31 , 32 .…”

Section: Introductionmentioning

confidence: 94%

Composites cement/BaSO4/Fe3O4/CuO for improving X-ray absorption characteristics and structural properties

Gharissah

Ardiansyah

Pauziah

et al. 2022

Sci Rep

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Composite cement/BaSO4/Fe3O4/CuO with a thickness of 0.6 cm for various amounts of CuO: 2 wt%, 4 wt%, 6 wt%, and 8 wt% were successfully synthesized for the X-ray radiation shield. The bonding characteristics of composite and structural properties were determined using Fourier transform infrared spectra for the wavelength range of 4000–400 cm−1 and X-ray diffraction with the range of 2θ from 25° to 50°, respectively. The shielding ability was measured using a mobile X-ray with an energy of 55, 66, and 77 keV for determining the mass and linear attenuation coefficient, electronic and atomic cross-section. These shield characteristics best agreement with theoretical calculation from the XCOM database for energy < 77 keV with half value layer (HVL) < 0.3 cm. The best shielding in this study indicated by the lowest HVL and MFP is composite for CuO 8 wt%. The HVL and MFP shows better values compared to the previous reported using composite rubber-based, indicated high potentials composite in this study for design new and efficient radiology rooms as an alternative concrete, especially for X-ray radiation, in the future.

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Important parameters derived from Monte Carlo (MC) and Molecular Dynamics (MD) simulations

Singh¹,

Beg²,

Dewangan³

et al. 2023

Computational Modelling and Simulations for Designing of Corrosion Inhibitors

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Performance estimation of lead-free dual-layered shielding in dismantling of steam generator: A Monte-Carlo simulation study

Cited by 4 publications

References 26 publications

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

Composites cement/BaSO4/Fe3O4/CuO for improving X-ray absorption characteristics and structural properties

Important parameters derived from Monte Carlo (MC) and Molecular Dynamics (MD) simulations

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