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Andon Insani

Research Center for Nuclear Reactor Technology-BRIN

SCHOLARLY PAPERS

3

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119

TOTAL CITATIONS

0

Scholarly Papers (3)

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1.

Residual Stress Analysis in Ods Fenicry2o3 Alloys for Very High Temperature Reactors: A Neutron Diffraction Study

Number of pages: 12 Posted: 27 Feb 2024
Parikin Farihin, Bambang Suharno, Mohammad Dani, I. Wayan Ngarayana, Andryansyah Andryansyah, Andon Insani, Dian Adi Prastowo, Diene Noor Haerani, Nanda Shabrina and Rai Indra Wardana
affiliation not provided to SSRN, University of Indonesia Jl. Margonda Raya, Pondok Cina, Beji, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, Research Center for Nuclear Reactor Technology-BRIN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 56 (1,000,027)

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FeNiCr alloys, ODS, Y2O3, microstructure, neutron diffraction, residual stress, very high temperature nuclear reactor.

2.

Neutronic Performance of Oxide Dispersion Strengthened Fe–25Ni–17Cr Austenitic Alloy as Advanced Fuel Cladding Material for Light Water Reactors

Number of pages: 25 Posted: 08 Nov 2025
Parikin Farihin, Ferhat Aziz, Parikin Farihin, Andon Insani, Mardiyanto Panitra, Andryansyah Andryansyah, Elfrida Saragi, Almira Citra Amelia, Farisy Yogatama Sulistyo, Muhammad Subhan, I. Wayan Ngarayana, Topan Setiadipura, Damar Rastri Adhika, Bambang Suharno and Ching An Huang
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, Research Center for Nuclear Reactor Technology-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, University of Indonesia Jl. Margonda Raya, Pondok Cina, Beji and Chang Gung University
Downloads 47 (1,097,529)

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Oxide dispersion strengthened, Fe-25Ni-17Cr, Doppler coefficient, Neutronic performance, Nuclear safety, Accident tolerant fuel

3.

Microstructural Evolution and Irradiation-Induced Degradation Mechanisms of AlMg3 Under Long-Term Neutron Exposure In the RSG-GAS Research Reactor

Number of pages: 19 Posted: 12 May 2026
Dicky Tri Jatmiko, Heri Hermansyah, Geni Rina Sunaryo, Abdul Aziz, Tantri Prasetyani, Andon Insani, Roziq Himawan and A. Setiawan
University of Indonesia (UI), University of Indonesia, Research Center for Nuclear Reactor Technology-BRIN, Research Center for Radiation Processing Technology-BRIN, Nuclear Facilities Management-BRIN, Research Center for Nuclear Reactor Technology-BRIN, Research Center for Radiation Processing Technology-BRIN and Science and Technology Park
Downloads 16 (1,509,872)

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structural integrity, neutron irradiation, AlMg3 alloy, irradiation-induced degradation, radiation-enhanced diffusion