Determination and calculation of gamma and neutron shielding characteristics of concretes containing different hematite proportions

Gençel, Osman; Bozkurt, Ahmet; Kam, Erol; Korkut, Turgay

doi:10.1016/j.anucene.2011.08.010

Cited by 168 publications

(50 citation statements)

References 15 publications

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“…Co-60 gama radyoizotop kaynağı 5.23 yıl yarı ömre sahip olup 1.17 ve 1.33 MeV enerjilerinde iki farklı gama radyasyonu yayınlamaktadır [14]. Teorik hesaplamalarda Co-60 gama radyoizotopuna ilişkin ortalama enerji değeri 1.25 MeV olarak kabul edilebilmektedir [7]. Bu bağlamda Co-60 gama radyoizotopu radyasyonunun madde ile etkileşmesi olaylarında gelen gama ışınlarının minimum 1.02 MeV enerjili olması durumunda ortaya çıkabilen, çift oluşumu olayıda kendini göstermektedir [15].…”

Section: Deneysel çAlışmalarunclassified

Investigation on the Behaviours of TiB2 Reinforced B4C-SiC Composites Against Co-60 Gamma Radioisotope Source

Büyük¹,

Tuğrul²

2015

Pamukkale J Eng Sci

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Section: Deneysel çAlışmalarunclassified

Investigation on the Behaviours of TiB2 Reinforced B4C-SiC Composites Against Co-60 Gamma Radioisotope Source

Büyük¹,

Tuğrul²

2015

Pamukkale J Eng Sci

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“…Another point about popularity of concrete is its hydrogen content for neutron shielding. The importance of hydrogen in concrete, in terms of radiation (particularly neutrons) shielding process, is known [9,11,12]. There are many studies on concretes containing different nonPb materials.…”

Section: Introductionmentioning

confidence: 99%

Production of Barite and Boroncarbide Doped Radiation Shielding Polymer Composite Panels

Evcin

Bezir

et al. 2017

Acta Phys. Pol. A

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Developments in nuclear technology in the last century have lead to the use of radiation in different areas of human activity. These are not just the energetics but also food, agriculture, medicine, industry and science. Thus, radiation has become an inevitable phenomenon in our lives. Since we cannot isolate radiation from our life, the radiation protection methods should be available. As alternatives to conventional radiation prevention methods, such as lead and heavy concrete shielding, more functional materials need to become the focus of research. The development of the least harmful to the environment, easily applicable, flexible radiation shields has become very important. In this study, silicon matrix composite panels, doped with different ratios of barite and boron carbide, were produced and characterized by optical and scanning electron microscopy (SEM). Gamma and neutron radiation shielding properties of these materials were investigated. The results have been compared with the lead as the standard shielding material.

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“…Sehingga diperlukan unsur-unsur tambahan di dalam perisai radiasi yang dapat menahan atau menangkap neutron secara efektif. Diantara unsur-unsur tambahan tersebut yang dapat menangkap radiasi neutron dengan sangat baik adalah boron, cadmium dan lain-lain yang memiliki tampang lintang tangkapan neutron yang besar [12,13,14]. Pada penelitian ini digunakan beton yang mengandung senyawa boron [15,16,17] sebagai perisai radiasi tambahan di depan tabung berkas yaitu jenis beton Boron Frits-baryte setebal 280 cm.…”

Section: Jarak Radial Dari Tengah Teras (Cm)unclassified

Desain Konseptual Perisai Radiasi Reaktor Rri-50

Hamzah

Kuntoro

2015

Tri Dasa Mega

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ABSTRAKDESAIN KONSEPTUAL PERISAI RADIASI REAKTOR RRI-50. Salah satu parameter yang harus dipenuhi dalam mendesain reaktor nuklir adalah desain perisai radiasi yang dapat menjamin keamanan dan keselamatan radiasi bagi pekerja dan masyarakat sekitar. Pada penelitian ini dilakukan desain perisai radiasi RRI-50 dengan elemen bakar berjenis U9Mo-Al berkerapatan tinggi dengan tipe pelat sebanyak 21 buah dan berdimensi seperti elemen bakar RSG-GAS tapi panjang aktifnya 70 cm. Konfigurasi teras terdiri dari 16 elemen bakar dan 4 elemen kendali serta 5 posisi iradiasi sehingga membentuk matriks 5 x 5. Tujuan dari penelitian ini adalah mendesain perisai radiasi dan menentukan distribusi laju dosis di daerah kerja dan di lingkungan reaktor RRI-50. Tahapan awal penelitian adalah perhitungan kuat sumber dan inventori bahan radioaktif teras reaktor dengan mensimulasikan operasi 50 MW selama 20 hari tiap siklus menggunakan program ORGEN2.1. Berdasarkan kuat sumber tersebut dan model yang dibuat menggunakan program VisEd, maka dilakukan analisis penentuan parameter perisai radiasi secara iteratif menggunakan program MCNPX. Pada tahap akhir, dilakukan analisis distribusi laju dosis di seluruh ruang di dalam dan di luar gedung reaktor juga menggunakan program MCNPX. Hasil yang diperoleh menunjukkan bahwa ketinggian permukaan air adalah 1000 cm dan kombinasi 90 cm beton berat dan 60 cm beton biasa dapat digunakan sebagai perisai biologi. Desain perisai tersebut mereduksi laju dosis menjadi 0,05 µSv/jam di Balai Operasi sementara di Balai Eksperimen dan di luar gedung reaktor menjadi 4,2 µSv/jam dan 0,03 µSv/jam pada saat reaktor beroperasi. Hasil penelitian juga menunjukkan pemasagan perisai tambahan setebal 280 cm berjarak 300 cm di depan tabung berkas neutron radial yang terbuka mereduksi laju dosis gamma dan neutron menjadi 3,3 µSv/jam dan 3,1x10 -11 µSv/jam. Hasil-hasil penelitian ini menunjukkan bahwa desain perisai radiasi yang dibuat membuat reaktor RRI-50 menjadi aman dari bahaya radiasi bagi pekerja dan masyarakat sekitarnya.Kata kunci : Perisai radiasi, laju dosis, keselamatan radiasi, RRI-50. ABSTRACT RADIATION SHIELDING CONSEPTUAL DESIGN OF RRI-50 REACTOR. One of the parameters that must be met in the design of nuclear reactors is radiation shielding design to ensure the security and safety of workers and the surrounding community. This study has been conducted to design radiation shielding of RRI-50 with high density U9Mo-Al fuel elements that consist of 21 pieces of plate type fuel elements with dimension as same as RSG-GAS fuel elements but the active length is 70 cm. Core configurations consist of 16 fuel elements and 4 control elements and 5 irradiation positions to form a matrix of 5 x 5. The objective of this research is to design radiation shielding and determine the distribution of dose rates in the working

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Determination and calculation of gamma and neutron shielding characteristics of concretes containing different hematite proportions

Cited by 168 publications

References 15 publications

Investigation on the Behaviours of TiB2 Reinforced B4C-SiC Composites Against Co-60 Gamma Radioisotope Source

Investigation on the Behaviours of TiB2 Reinforced B4C-SiC Composites Against Co-60 Gamma Radioisotope Source

Production of Barite and Boroncarbide Doped Radiation Shielding Polymer Composite Panels

Desain Konseptual Perisai Radiasi Reaktor Rri-50

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