Neutron Shielding for Cf-252 Source: FLUKA Simulations and Measurements
IRANIAN JOURNAL OF SCIENCE AND TECHNOLOGY TRANSACTION A-SCIENCE, cilt.46, sa.3, ss.1055-1064, 2022 (SCI-Expanded, Scopus)
- Yayın Türü: Makale / Tam Makale
- Cilt numarası: 46 Sayı: 3
- Basım Tarihi: 2022
- Doi Numarası: 10.1007/s40995-022-01318-1
- Dergi Adı: IRANIAN JOURNAL OF SCIENCE AND TECHNOLOGY TRANSACTION A-SCIENCE
- Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus, ABI/INFORM, Aerospace Database, Aqualine, Aquatic Science & Fisheries Abstracts (ASFA), BIOSIS, CAB Abstracts, Communication Abstracts, zbMATH
- Sayfa Sayıları: ss.1055-1064
- Anahtar Kelimeler: FLUKA simulation, Neutron shielding, Cf-252, METAL OXIDE GLASSES, GAMMA-RADIATION, CROSS-SECTIONS, CONCRETE, ATTENUATION
- Süleyman Demirel Üniversitesi Adresli: Evet
Özet
Neutron is an important particle and may be emitted by unstable nuclei or after some nuclear applications through nuclear reactions. It is uncharged and thus this makes its detection and shielding is more difficult than other particles. As the neutron is also more dangerous than other radiation types such as proton and electron or gamma rays, it is important to develop efficient shielding materials in order to be protected from its hazardous effects. In this work, the shielding properties of container which contains configuration of polyethylene, barite, lead, and iron have been investigated against Cf-252 source. This was done by experimental work and then compared with the calculations done using FLUKA code.