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"Beton dan timbal merupakan material yang biasa digunakan sebagai dinding penahan radiasi. Beton dan timbal memiliki kelebihan dan kekurangannya masing-masing. Beton memiliki harga yang relatif lebih murah namun memerlukan ruang yang besar sedangkan timbal dengan nomor atom yang tinggi memiliki harga yang lebih mahal namun ukuran ruangan dapat diminimalisir. Perhitungan ketebalan dinding penahan radiasi dapat dilakukan dengan menggunakan persamaan Safety Report Series No. 47 dengan nilai pembatas dosis sesuai dengan Perka Bapeten no 3 tahun 2013 lalu dilakukan pemodelan menggunakan Monte Carlo EGSnrc untuk memastikan nilai dosis yang dihasilkan tidak melebihi pembatas dosis yang ditetapkan Bapeten. Pemodelan dengan menggunakan Monte Carlo umum digunakan ketika pengukuran secara langsung tidak memungkinkan. Hasil simulasi Monte Carlo juga mampu merepresentasikan kondisi yang sesungguhnya dengan memasukan berbagai parameter seperti memodelkan linac, memodelkan material yang digunakan, memodelkan dinding penahan radiasi, hingga melakukan kalibrasi linac sehingga didapatkan nilai dosis yang dapat dibandingkan dengan nilai dosis referensi yang digunakan. Pada penelitian dilakukan perhitungan dosis di luar dinding primer dengan memodelkan dinding beton densitas 2,35 g/cm3 dengan ketebalan 1,45 meter dan dinding timbal densitas 11,35 g/cm3 dengan ketebalan 21,73 cm lalu dibandingkan dengan nilai dosis referensi yang ditetapkan oleh Bapeten. Hasilnya nilai dosis pada simulasi Monte Carlo EGSnrc untuk material beton dan timbal lebih rendah dibandingkan dengan nilai dosis referensi yang digunakan akibat perbedaan komposisi material penyusun beton dan timbal yang digunakan dalam simulasi dengan referensi

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Concrete and lead are materials commonly used as primary radiation walls. Concrete and lead have their respective advantages and disadvantages. Concrete has a relatively cheaper price but requires a large space, while lead with a high atomic number has a higher price, but the size of the room can be minimized. Calculation of the thickness of the radiation retaining wall can be carried out using the Safety Report Series No. 47 equations with a dose limiting value in accordance with Perka Bapeten Number 3. Of 2013 and then modeling using the Monte Carlo EGSnrc to ensure the resulting dose value does not exceed the limiting dose value by Bapeten. Monte Carlo modeling is commonly used when direct measurements are not possible. The Monte Carlo simulation results are also able to represent the real conditions by entering various parameters such as modeling the linac, modeling the materials used, modeling the primary radiation walls, and performing the linac calibration so that a dose value can be compared with reference dose value used. In this study, the dose calculation outside the primary wall was carried out by modeling a concrete wall with a density of 2,35 g/cm3 with a thickness of 1,45 meters and a lead wall with a density of 11,35 g/cm3 with a thickness of 21,73 cm and then compared with the reference dose value set by Bapeten. The result is that the dose value in the Monte Carlo EGSnrc simulation for concrete and lead materials is lower than the reference dose value used due to differences in the composition of the concrete and lead materials used in the simulation with reference"

"International Atomic Energy Agency (IAEA) mengeluarkan rekomendasi kepada badan pengawas untuk menunjuk Petugas Proteksi Radiasi (PPR) yang berkompeten di radiologi diagnostik dan intervensional (RDI). Penelitian bertujuan mengetahui kompetensi (pengetahuan, keterampilan dan sikap) PPR, faktor yang berpengaruh, indikator pengetahuan, keterampilan dan sikap yang signifikan serta hubungan antar variabel pengetahuan, keterampilan dan sikap. Rancangan penelitian rancangan cross sectional bersifat deskriptif kuantitatif. Hasil penelitian menunjukkan 41,6 % PPR memiliki tingkat kompetensi rata rata 69,0 dengan kategori sedang. Faktor mempengaruhi pengetahuan adalah latar belakang pendidikan, pekerjaan selain sebagai PPR di RS, perlengkapan keselamatan radiasi, paparan informasi, frekuensi rekualifikasi, pelatihan serta komitmen pemegang izin. Faktor mempengaruhi keterampilan adalah peminatan studi/jurusan, pekerjaan selain sebagai PPR di RS, perlengkapan keselamatan radiasi, sumber informasi, frekuensi rekualifikasi, pelatihan serta komitmen pemegang izin. Faktor yang mempengaruhi sikap adalah tingkat pendidikan, peminatan studi/jurusan, umur, seberapa sering bekerja dengan radiasi, perlengkapan dan komitmen pemegang izin. Hasil uji multivariat diperoleh indikator pengetahuan yang signifikan adalah pengetahuan tentang konsep verifikasi kesesuaian dan kepatuhan persyaratan dan standar proteksi dan keselamatan radiasi. Indikator keterampilan yang signifikan adalah keterampilan menyusun dokumen program proteksi dan keselamatan radiasi dan Indikator sikap signifikan adalah pro aktif mendorong dokter radiologi untuk menetapkan kriteria pemeriksaan yang boleh, yang dilarang dan yang perlu konsultasi dokter. Pengetahuan berpengaruh signifikan terhadap keterampilan, pengetahuan berpengaruh signifikan terhadap sikap dan keterampilan berpengaruh signifikan terhadap sikap. Hasil penelitian menyarankan adanya perbaikan pada unit kompetensi, persyaratan sertifikasi, mekanisme penyegaran, pembuatan SKKNI PPR dan pelatihan berkelanjutan bagi PPR di fasilitas RDI.

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The International Atomic Energy Agency (IAEA) urges regulatory organizations to hire a radiation protection officer (PPR) who is proficient in both diagnostic and interventional radiology (RDI). This research aimed to determine the competency (knowledge, skills and attitudes) of PPR, influencing factors, significant indicators of knowledge, skills and attitudes and the relationship between knowledge, skills and attitudes variables. The research employed descriptive quantitative method with a cross sectional design. The findings revealed that average competency score is 69,0 had moderate levels. Knowledge is influenced by educational background, occupation other than PPR in hospitals, radiation safety equipment, exposure to information, frequency of requalification, training and commitment of permit holders. Meanwhile, skills are influenced by study/departmental specialization, work other than PPR in hospitals, radiation safety equipment, sources of information, frequency of requalification, training and commitment of permit holders. In addition, attitudes influenced by education level, study/department interest, age, how often to work with radiation, equipment and permit holder commitment. The multivariate test results revealed that comprehending the idea of validating conformity and compliance with radiation protection and safety criteria and standards was a significant indicator of knowledge. A significant skill indication is the skill to compile radiation protection and safety program documentation. Significant attitude indication is actively encouraging radiology doctors to establish standards for examinations that are allowed, prohibited, and require medical consultation. Knowledge has a significant effect on skills, skills have a significant effect on attitudes, and attitudes have a significant effect on knowledge. The research suggest improvements to competency units, certification requirements, refresher mechanisms, making SKKNI PPR and ongoing training for PPR at RDI facilities."

"This completely updated second edition of Radiation exposure and image quality in x-ray diagnostic radiology provides the reader with detailed guidance on the optimization of radiological imaging. The basic physical principles of diagnostic radiology are first presented in detail, and their application to clinical problems is then carefully explored. The final section is a supplement containing tables of data and graphical depictions of X-ray spectra, interaction coefficients, characteristics of X-ray beams, and other aspects relevant to patient dose calculations. In addition, a complementary CD-ROM contains a user-friendly Excel file database covering these aspects that can be used in the reader’s own programs. "

"Salah satu upaya perlindungan dari potensi bahaya radiasi di lingkungan sebagai dampak dari adanya lepasan radiasi disekitar fasilitas nuklir adalah dengan pemantauan dosis radiasi di lingkungan secara waktu nyata dan terus-menerus. Penelitian ini mengkaji sistem pemantaun radiasi di lingkungan yang telah diterapkan saat ini, kemudian mengembangkan sistem tersebut agar lebih berdayaguna dalam rangka kesiapsiagaan nuklir. Pengembangan sistem dilakukan melalui penambahan jaringan sensor nirkabel dan fitur peringatan dini.Jaringan sensor nirkabel JSN yang diaplikasikan kedalam sistem, meliputi JSN berbasis radio frekuensi RF dan general packet radio service GPRS. Faktor koreksi hasil pengukuran JSN GPRS tipe Pancake terhadap peralatan komersial JSN RF untuk pengukuran paparan radiasi lingkungan adalah 0.657, sedangkan faktor koreksi JSN GPRS tipe NaI Tl adalah 0,502. Data yang dikirim oleh perangkat deteksi gamma dikumpulkan di server yang dikelola oleh Pusat Pendayagunaan Informatika dan Kawasan Strategis Nuklir PPIKSN-BATAN. Data yang diterima server disimpan di database xmonitoring, dapat dilihat secara langsung nilai paparan radiasi di lingkungan melalui phpmyadmin. Disain website dapat dikunjungi pada alamat http: 223.25.97.90/radmon-farid/index.php. Sistem peringatan dini akan dikirimkan ke operator penanggungjawab sistem radmon, apabila parameter pembatas paparan radiasi lingkungan sebesar 0,3 ?Sv/jam terlampaui. SMS peringatan dini akan dikirimkan kepada operator sistem radmon setelah 15 - 60 detik data pengukuran paparan radiasi lingkungan diterima oleh server.

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One effort to protection from increasing of potentially environmental radiation hazards as impact of radiation discharge around nuclear facilities by environmental radiation monitoring in real time and continuously. This research focus on radiation monitoring sistem, then develop this sistem more efficiently for nuclear preparedness. This system was developed through addition of wireless sensor networks and early warning features. Wireless sensor networks WSN was applied to this system, including WSN based on radio frequency RF and general packet radio service GPRS. The correction factor of WSN GPRS Pancake type measurement results compare to WSN RF commercial equipment for environmental radiation exposure is 0.657, and correction factor for WSN GPRS NaI Tl type is 0.502. Data has been collected on the servers, who manage by Center for Informatics and Nuclear Strategic Zone Utilization BATAN Serpong. The value of doserate data was received of the server will be viewed on the graph of the website, with address 223.25.97.90 radmon farid index.php. This system will be sent to the radmon operator, if the parameters of threshold environmental radiation level was exceeded from 0.3 Sv h. after 15 60 seconds of measurement data of environmental radiation exposure received by the server. SMS early warning will be delivered to the operator this system, after 15 60 seconds environmental radiation exposure measurement was received."

"Penelitian ini bertujuan untuk memberikan solusi penyimpanan Bahan Bakar Nuklir Bekas (SNF) di Indonesia. Karena keterbatasan ruang pada penyimpanan tipe basah, maka penelitian ini merancang, mensimulasikan, melakukan eksperimen, dan menghitung biaya pembuatan penyimpanan dry cask storage secara simultan. Dalam studi ini, desain dry cask storage dioptimalkan dengan menggunakan dua objective functions secara bersamaan yaitu fungsi keselamatan (yang menggabungkan parameter kekritisan, proteksi radiasi dan penghilangan panas) dan fungsi biaya. Perhitungan optimasi kemudian divalidasi dan dianalisis dengan data eksperimen dari prototipe dry cask storage. Dengan menentukan decision variables dan constraints, kemudian memasukkannya ke dalam Matlab software, diperoleh tiga pilihan hasil optimasi, safety optimized, cost optimized dan multi-objective optimized. Dalam multi-objective optimized, desain penyimpanan kering yang optimal diperoleh untuk radius luar beton dan timbal (Pb) masing-masing sebesar 0,06 m dan 0,51 m. tinggi ventilasi dan lebar masing-masing sebesar 0,15 m dan 0,5 m, dan perbedaan ketinggian ventilasi sebesar 2,43 m. Untuk kelima variabel diatas, nilai optimum temperatur permukaan kanister adalah 66,8 °C dan biaya yang dibutuhkan untuk pembuatan dry cask storage adalah $147,827. Ketebalan material yang dibutuhkan didapatkan nilai yang paling optimum untuk Pb 0,06 m dan beton 0,51 m, dari validasi menggunakan MicroShield software didapatkan paparan permukaan penyimpanan dry cask sebesar 104,8 mR/jam sehingga masih dalam batas aman dari nilai maksimum yang ditentukan yaitu 160 mR/jam. Demikian pula dari simulasi suhu permukaan tabung menggunakan Ansys Fluent software untuk kelima variabel di atas, nilai suhu permukaan mendekati perhitungan yang persamaannya dimasukkan ke dalam Matlab software. Validasi menggunakan data eksperimen dari prototipe dry cask storage dan juga perhitungan manual diperoleh nilai temperatur yang juga relatif mendekati hasil optimasi, yaitu 45,2 °C untuk temperatur dari eksperimen dan 50.2 °C untuk temperatur perhitungan teori. Hasil nilai optimasi terpilih dengan tetap menjaga keamanan termal menunjukkan bahwa acuan dalam pembuatan desain dengan skala 1:1 dapat menggunakan estimasi untuk keamanan termal T1, untuk jenis SNF Materials Testing Reactor (MTR) dengan umur setelah sepuluh tahun disimpan pada jenis penyimpanan tipe basah.

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This research aims to provide a solution for Indonesia's spent nuclear fuel (SNF) storage. Due to the limited storage space in wet type storage, this research designs, simulates, conducts experiments, and calculates the cost of making dry cask storage simultaneously. In this study, the dry storage design was optimized by using two objective functions simultaneously: safety function (which combines criticality parameters, radiation protection and heat removal) and cost function. The optimization calculations were then validated and analyzed with experimental data from the dry cask storage prototype. By determining the decision variables and constraints and then inputting them into the Matlab software, three choices of optimization results are obtained, safety optimized, cost optimized and multi-objective optimized. In multi-objective optimized, the optimum dry storage design is obtained for the concrete outer- and lead (Pb) outer-radius of 0.06 m and 0.51 m respectively. vent-height, -widt by 0.15 m and 0.5 m respectively, and a vent elevation difference of 2.43 m. For the five variables above, the optimum value for the canister surface temperature is 66.8 °C and the cost required to make dry storage is $ 147,827.The required thickness of the material obtained the most optimum value for Pb 0.06 m and concrete 0.51 m, from validation using MicroShield software, it was obtained that the dry cask storage surface exposure was 104.8 mR/h so that it is still within the safe limit of the maximum value specified, which is 160 mR/h. Similarly, from the simulation of canister surface temperature using Ansys Fluent for the five variables above, the surface temperature value is close to the calculation whose equations are inputted into matlab. Validation using experimental data from the dry storage prototype and also manual calculations obtained temperature values which are also relatively close to the optimization results, 45.2 °C for temperature from experiments and 50.2 °C for temperature from manual calculations. The result of the selected optimization value while maintaining thermal safety indicates that reference in making designs with a scale of 1:1 can use the estimate for the thermal safety of T1, for the type of SNF Materials Testing Reactor with age after ten years stored in the wet storage type."

"This book presents a selection of essential issues that have been prioritized in the occupational and environmental area in 2019. It covers both research and best industrial practices in five main fields, i.e. occupational and environmental safety; occupational and environmental hygiene; occupational and environmental health; ergonomics and biomechanics; and psychosocial issues. In addition to this, other works were selected in transversal and emergency areas. Important issues in training, management, robotics, industry 4.0 have also been addressed. The different chapters aimed at covering the perspective of all involved people, such as managers, workers and OSH professionals. This book is intended as a timely reference guide and source of inspiration to OSH researchers, practitioners and organizations operating in a global and international context."