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Deni Mustika

affiliation not provided to SSRN

SCHOLARLY PAPERS

3

DOWNLOADS

121

TOTAL CITATIONS

0

Scholarly Papers (3)

1.

Flexible Lead-Free Gamma-Ray Radiation Shielding using La(OH)3-Enhanced Natural Rubber Composites

Number of pages: 37 Posted: 17 Sep 2025
National Research and Innovation Agency (BRIN), affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, Universitas Andalas, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 65 (916,100)

Abstract:

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Radiation shielding, Lanthanum hydroxide, La/NR composite, Half-value Layer, Gamma-ray attenuation

2.

Neutronic Analysis of U-7Mo-xTi/Al Fuel Elements as Replacement Candidates for Indonesia’s RSG-GAS Research Reactor Fuel: Enrichment Optimisation, Burnup Behaviour, and Temperature Coefficients

Number of pages: 29 Posted: 02 Oct 2025
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 38 (1,209,354)

Abstract:

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neutronic, RSG-GAS, U-7Mo-Ti, U3Si2, nuclear fuel, burnup, OpenMC

3.

Neutronic Analysis of U-7mo-Xti/Al Fuel Elements as Replacement Candidates for Indonesia's Rsg-Gas Research Reactor Fuel: Enrichment Optimization, Burnup Behavior, and Temperature Coefficients

Number of pages: 27 Posted: 13 Jun 2025
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 18 (1,470,786)

Abstract:

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neutronic, RSG-GAS, U-7Mo, U3Si2, nuclear fuel, burnup, OpenMC