Gamma-ray and neutron shielding capability of blended cement-stabilized barite fillers developed by maximum density method
Özet
The disposal of radiological wastes in the deep geological repositories has become an important issue for the reduction of hazardous risks on the human and biological environments. In this study, blended cement-stabilized barite fillers against gamma rays and neutrons have been developed with the use of the maximum density method by considering various amounts of water (100–300 kg/m3), binder (4–10%), and compaction energy (500–2000 kJ/m3). According to the experimental series of these filler materials, satisfactory response surface results have been achieved in the study. The experimental results revealed that compacted filling material can ensure an efficient shielding capability for gamma rays and neutrons when designed with a density of 3.064 g/cm3. An increase in binder content, water content, and compaction energy has improved the compressive strength of these materials up to 37 times according to that of the poorest series. Neutron and gamma-ray shielding capabilities were found to be 119 and 14% higher than those of the poorest filler material, respectively when theoretical and experimental results are considered in the study.
Anahtar Kelimeler
- Scopus
- 4
- WoS
- 3
- OpenAlex
- 5
Tam Kayıt
| Alan | Değer | Dil |
|---|---|---|
| dc.contributor.author | Gökçe, H.S. | |
| dc.contributor.author | Öksüzer, N. | |
| dc.contributor.author | Kamiloğlu, H.A. | |
| dc.contributor.author | Yılmaz, F. | |
| dc.date.accessioned | 2026-10-29T19:10:21.478045817Z | |
| dc.date.available | 2026-10-29T19:10:21.478045817Z | |
| dc.date.issued | 2023 | |
| dc.description.abstract | The disposal of radiological wastes in the deep geological repositories has become an important issue for the reduction of hazardous risks on the human and biological environments. In this study, blended cement-stabilized barite fillers against gamma rays and neutrons have been developed with the use of the maximum density method by considering various amounts of water (100–300 kg/m3), binder (4–10%), and compaction energy (500–2000 kJ/m3). According to the experimental series of these filler materials, satisfactory response surface results have been achieved in the study. The experimental results revealed that compacted filling material can ensure an efficient shielding capability for gamma rays and neutrons when designed with a density of 3.064 g/cm3. An increase in binder content, water content, and compaction energy has improved the compressive strength of these materials up to 37 times according to that of the poorest series. Neutron and gamma-ray shielding capabilities were found to be 119 and 14% higher than those of the poorest filler material, respectively when theoretical and experimental results are considered in the study. | |
| dc.identifier.articlenumber | 104743 | |
| dc.identifier.doi | 10.1016/j.pnucene.2023.104743 | |
| dc.identifier.eissn | 1878-4224 | |
| dc.identifier.issn | 0149-1970 | |
| dc.identifier.scopus | 2-s2.0-85159555666 | |
| dc.identifier.uri | https://rdlopen.rawdatalibrary.net/r/bayburt/13016 | |
| dc.identifier.volume | 161 | |
| dc.identifier.wos | WOS:001009285700001 | |
| dc.language.iso | en | |
| dc.publisher | Elsevier Ltd | |
| dc.relation.ispartof | Progress in Nuclear Energy | |
| dc.rights | info:eu-repo/semantics/closedAccess | |
| dc.subject | Anti-radiation filler | |
| dc.subject | Gamma-ray and neutron shielding capability | |
| dc.subject | Maximum density method | |
| dc.subject | Physical and mechanical properties | |
| dc.subject | Stabilization with blended cement | |
| dc.subject.classification | Nuclear Science & Technology | |
| dc.subject.other | Barite | |
| dc.subject.other | Cements | |
| dc.subject.other | Compressive strength | |
| dc.subject.other | Fillers | |
| dc.subject.other | Gamma rays | |
| dc.subject.other | Neutrons | |
| dc.subject.other | Radiation shielding | |
| dc.subject.other | Waste disposal | |
| dc.subject.other | Anti radiations | |
| dc.subject.other | Anti-radiation filler | |
| dc.subject.other | Blended cement | |
| dc.subject.other | Density methods | |
| dc.subject.other | Gamma-ray and neutron shielding capability | |
| dc.subject.other | Gamma-ray shielding | |
| dc.subject.other | Maximum density | |
| dc.subject.other | Maximum density method | |
| dc.subject.other | Neutron shielding | |
| dc.subject.other | Physical and mechanical properties | |
| dc.subject.other | Shielding capability | |
| dc.subject.other | Stabilization with blended cement | |
| dc.subject.other | Density (specific gravity) | |
| dc.title | Gamma-ray and neutron shielding capability of blended cement-stabilized barite fillers developed by maximum density method | |
| dc.type | Article | |
| rdl.citation.openalex | 5 | |
| rdl.citation.scopus | 4 | |
| rdl.citation.wos | 3 | |
| rdl.oa.status | closed | |
| rdl.scopus.quartile | Q1 | |
| rdl.source.index | SCOPUS | |
| rdl.source.index | WOS | |
| rdl.wos.index | Science Citation Index Expanded (SCI-EXPANDED) |
