Judul: Simulasi Monte Carlo Perisai Radiasi Proton dengan Variasi Beton Menggunakan Particle and Heavy Ion Transport code System (PHITS)
Abstrak: Perisai radiasi proton merupakan pelindung fisik yang digunakan untuk mengurangi laju radiasi pada lingkungan sekitar. Material yang paling umum digunakan sebagai perisai adalah beton. Penggunaan sotware berbasis Monte Carlo sebagai simulasi transportasi partikel banyak digunakan dalam bidang medis dan fisika nuklir, salah satunya perisai radiasi. Penelitian ini melakukan simulasi numerik menggunakan software PHITS berbasis monte carlo untuk mengetahui redaman proton saat melewati perisainya dengan variasi energi proton, jumlah partikel, ketebalan material perisai, jarak antara sumber dan perisai, dan jenis material perisai. Hasil simulasi yang didapatkan menunjukkan bahwa variasi terbaik yang didapatkan dalam perancangan perisai untuk terapi proton adalah material dengan dua lapisan, dimana lapisan 1 adalah beton (ρ=5,0 g/cm3) dan lapisan 2 adalah besi (ρ=7,0 g/cm3), dengan ketebalan perisai 10 cm dan jarak antara sumber dan perisai 20 cm, untuk material satu lapisan didapatkan perisai terbaik dengan densitas beton (ρ=2,31 g/cm3), dengan ketebalan 50 cm dan jarak 100 cm., A proton radiation shield is a physical shield placed between the ionization source and the object or target to be protected to reduce the rate of radiation dose in the surrounding environment. The most common material used as a shield is concrete. In medical and nuclear physics field, such as radiation shielding, Monte-Carlo-based software is commonly utilized as a particle transport simulation. This study conducted a numerical simulation using PHITS software based on Monte Carlo to determine the attenuation of protons passed the shield with variations in the proton energy, the number of particles, the thickness of the shielding material, the distance between source and shielding, and the composition of the shielding material. The results show that the best shield design variation is with two layers of material, layer 1 is concrete (ρ = 5,0 g/cm3) and layer 2 is iron (ρ=7,0 g/cm3) with a thickness of 10 cm, and a distance of 20 cm between the source and shielding, and the best shield is obtained with one layer of material with a density (ρ=2,31 g/cm3), the thickness of 50 cm, and a distance of 100 cm.
Keyword: Concrete, Monte Carlo, PHITS, Proton, Radiation Shielding

Judul: Synthesis of Neutron Radiation Shields Based on Concrete With Variations of Sand Types
Abstrak: ABSTRACT VENANDA AGUSTINA. Synthesis of Neutron Radiation Shields Based on Concrete With Variations of Sand Types. Supervised by MOHAMMAD NUR INDRO, DJAMIL HUSIN and IWAN SUMIRAT. Neutron radiation is ionizing radiation which has a high penetrating power. So a radiation shield is needed to reduce the danger from neutron radiation. In this study, a neutron radiation shield was made from concrete with 3 different types of sand, namely lukulo sand, white bangka sand and black bangka sand. Concrete as a shield for neutron radiation is tested for its absorption ability using the film method. This experiment also uses Energy-dispersive X-ray spectroscopy (EDS) for elemental analysis. The test results show that the white bangka sand concrete has a good performance as a neutron radiation shield because it has a high attenuation coefficient and a high neutron cross-section. The linear attenuation coefficient of lukulo sand concrete, white bangka sand concrete and black bangka sand concrete were 0.182 cm-1, 0.548 cm-1 and 0.430 cm-1, respectively. The cross-section of the largest neutron is owned by the white bangka sand, then the black bangka sand and lukulo sand. Keywords: Attenuation coefficient, Concrete, Film method, Neutron radiation, Neutron radiation shielding, Radiasi neutron merupakan radiasi pengion yang memiliki daya tembus yang tinggi. Sehingga diperlukan perisai radiasi untuk mengurangi bahaya dari radiasi neutron. Pada penelitian ini dibuat perisai radiasi neutron dari beton dengan 3 jenis pasir berbeda yaitu pasir lukulo, pasir putih bangka dan pasir hitam bangka. Beton sebagai perisai radiasi neutron di uji kemampuan serapannya dengan menggunakan metode film. Eksperimen ini juga menggunakan Energy-dispersive X-ray spectroscopy (EDS) untuk analisis unsur. Hasil pengujian menunjukan bahwa beton dari pasir putih bangka memiliki kinerja yang baik sebagai perisai radiasi neutron karena memiliki nilai koefisien atenuasi yang tinggi serta tampang lintang neutron yang tinggi. Koefisien atenuasi linear dari beton pasir lukulo, beton pasir putih bangka dan beton pasir hitam bangka berturut-turut yaitu 0.182 cm-1, 0.548 cm-1 dan 0.430 cm-1. Tampang lintang neutron dari yang terbesar dimiliki pasir putih bangka, kemudian pasir hitam bangka dan pasir lukulo. Kata kunci: Beton, Koefisien atenuasi, Metode film, Perisai radiasi neutron, Radiasi neutron, Neutron radiation is ionizing radiation which has a high penetrating power. So a radiation shield is needed to reduce the danger from neutron radiation. In this study, a neutron radiation shield was made from concrete with 3 different types of sand, namely lukulo sand, white bangka sand and black bangka sand. Concrete as a shield for neutron radiation is tested for its absorption ability using the film method. This experiment also uses Energy-dispersive X-ray spectroscopy (EDS) for elemental analysis. The test results show that the white bangka sand concrete has a good performance as a neutron radiation shield because it has a high attenuation coefficient and a high neutron cross-section. The linear attenuation coefficient of lukulo sand concrete, white bangka sand concrete and black bangka sand concrete were 0.182 cm-1, 0.548 cm-1 and 0.430 cm-1, respectively. The cross-section of the largest neutron is owned by the white bangka sand, then the black bangka sand and lukulo sand. Keywords: Attenuation coefficient, Concrete, Film method, Neutron radiation,
Keyword: Attenuation coefficient, Concrete, Film method, Neutron radiation, Neutron radiation shielding

Judul: Etno-ornitologi Burung Kancilan Flores (Pachycephala nudigula nudigula Hartert 1897) pada Masyarakat Lio di Taman Nasional Kelimutu
Abstrak: Bare-throathed whistler is one of several wild birds in Kelimutu National Park (TNKL) that is believed to have correlation with Lio Community‟s belief. The estimation of Bare-throated whistler‟s population in Kelimutu National Park was about 186.41-1668.07 individual by the density about 0.0389-0.3481 ind/ha with the sex ratio 6.2:1 that spreaded on area with height of 1100 – 1600 masl. The characteristic of Bare-throated whistler‟s habitat is a natural forest with various canopy level, high plant species diversity and high density. The habitat characteristics related to the availability of food in the form of insects, cover, safety and a nesting site. Generally the most of Lio community knew the existence of Bare-throated whistler directly or from their parents‟ stories. The perceptions of Lio Community to the Bare-throated whistler‟s existence is generally support the conservation efforts. The perceptions construct the Lio Community‟s atitude that tend to be conservative to the existence of Bare-throated whistler. The attitude shown by their behavior that not cathing the Bare-throated whistler from the TNKL‟s area or the outside. The attitude have an important role to the existence of Bare-throated whistler in Kelimutu National Park‟s area.
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