Americium-beryllium shield container optimization with new high alloyed stainless steel and composite material using MCNPX code

Autor: Hooshmand Fini Ali, Kheradmand Saadi Mohsen, Athari Allaf Mitra

Publikováno v: Nuclear Technology and Radiation Protection, Vol 38, Iss 2, Pp 96-101 (2023)

In this paper the goal is to optimize a shield for the americium-beryllium radioactive source, which generates a mixed neutron and gamma-ray radiation field, using two different materials designed with simultaneous moderation and absorption of neu

Externí odkaz: https://doaj.org/article/04fc06f6a11b40599ffa2ee2545f134c

Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor.

Autor: Lotfalian, Mohammadreza, Athari Allaf, Mitra, Mansouri, Masoud

Publikováno v: Kerntechnik; Aug2024, Vol. 89 Issue 4, p383-399, 17p

Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant

Autor: Mirghaffari Reza, Jahanfarnia Gholamreza, Athari Allaf Mitra

Publikováno v: Nuclear Technology and Radiation Protection, Vol 32, Iss 4, Pp 320-326 (2017)

In recent years, extended studies are developed for investigation the effects of using nanofluids in NPP as coolant. CANDU-6 reactors have the potential to use nanofluid coolants because in these reactors, the moderator system is fully independent

Externí odkaz: https://doaj.org/article/ed2f39f2a5fe4042acf59219e12cd52c

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A proposal to design a new high volume standard air filter for efficiency calibration of HPGe detector.

Autor: Tourang, Mahdi, Hadadi, Asghar, Athari Allaf, Mitra, Sardari, Dariush

Publikováno v: Journal of Radioanalytical & Nuclear Chemistry; Jan2021, Vol. 327 Issue 1, p345-352, 8p, 3 Color Photographs, 2 Black and White Photographs, 6 Charts, 1 Graph