Installation and Operation of Ten-Kilocurie Cobalt-60 Gamma-Radiation Source

1954 ◽  
Vol 22 (2) ◽  
pp. 88-92 ◽  
Author(s):  
John V. Nehemias ◽  
L. E. Brownell ◽  
W. W. Meinke ◽  
E. W. Coleman
Keyword(s):  
Gamma Radiation ◽  
Radiation Source

scholarly journals PEMBUATAN SUMBER RADIASI GAMMA 137Cs DENGAN AKTIVITAS 20 mCi DARI PEB U3Si2-Al PASCA IRADIASI DALAM CONTAINER STAINLESS STEEL

2016 ◽  
Vol 21 (3) ◽  
Author(s):  
Aslina Br. Ginting ◽  
Yanlinastuti Yanlinastuti ◽  
Noviarty Noviarty ◽  
Boybul Boybul ◽  
Arif Nogroho ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Gamma Radiation ◽  
Cation Exchange ◽  
High Activity ◽  
Radiation Source ◽  
Solid Phase ◽  
Test Results ◽  
Spent Fuel ◽  
Post Irradiation ◽  
Outer Capsule

PEMBUATAN SUMBER RADIASI GAMMA ISOTOP 137Cs DENGAN AKTIVITAS 20 mCi DARI PEB U3Si2-Al PASCA IRADIASI DALAM CONTAINER STAINLESS STEEL. Kegiatan uji pasca iradiasi pelat elemen bakar (PEB) U3Si2-Al banyak menghasilkan larutan dengan keaktifan yang sangat tinggi. Larutan tersebut mengandung isotop 137Cs, uranium serta transuranium yang mempunyai waktu paroh panjang dan berbahaya bagi lingkungan. Namun larutan tersebut memiliki nilai ekonomis tinggi karena dapat dimanfaatkan sebagai bahan baku untuk pembuatan sumber radiasi sinar gamma isotop 137Cs. Hal ini dapat membantu bidang industri dalam memenuhi kebutuhan sumber radioaktif dalam negeri karena selama ini kebutuhan isotop 137Cs di Indonesia masih tergantung dari industri luar negeri. Selain itu, pengadaan dan transportasi isotop 137Cs dari luar negeri serta dalam penggunaannya memerlukan persyaratan yang cukup ketat dari Badan Pengawas Tenaga Nuklir Nasional (BAPETEN), sehingga menyebabkan harga isotop 137Cs menjadi mahal sampai di Indonesia. Dengan alasan tersebut, BATAN sebagai lembaga litbang nuklir di Indonesia perlu mempelajari pembuatan sumber radiasi gamma isotop 137Cs dari larutan hasil pengujian bahan bakar nuklir U3Si2-Al pasca iradiasi. Manfaat isotop 137Cs sangat luas antara lain digunakan dalam menganalisis sampel lingkungan, industri migas, konstruksi, radiografi, perikanan, rumah sakit dan pertambangan. Pembuatan sumber radiasi gamma isotop 137Cs dimulai dari pengumpulan larutan hasil pengujian PEB U3Si2-Al. Larutan larutan hasil pengujian mengandung isotop 137Cs dan isotop lainnya dikumpulkan menjadi satu dalam botol dengan volume 65 mL. Pemisahan isotop 137Cs dari hasil fisi lainnya dilakukan dengan metode penukar kation menggunakan zeolit Lampung dengan berat 45 gr. Hasil pemisahan diperoleh 137Cs-zeolit dalam fasa padat dan isotop lainnya berada dalam fasa cair. Padatan137Cs-zeolit kering kemudian kemudian ditimbang dan diukur aktivitasnya menggunakan spektrometer-g. Hasil analisis dengan spektrometer-g diperoleh aktivitas padatan 137Cs-zeolit sebesar 20 mCi. Untuk menjadi sumber radiasi gamma 137Cs, padatan 137Cs-zeolit dengan aktivitas 20 mCi dikemas dengan cara memasukkan ke dalam inner-outer capsule terbuat dari stainless steel yang telah dirancang sebelumnya. Container stainless steel diproses menjadi sumber radiasi gamma tertutup (shield source) untuk selanjutnya disertifikasi oleh PTKMR-BATAN sebagai lembaga kalibtrator bahan radioaktif di BATAN.Kata kunci: Larutan proses PEB U3Si2-Al, radioaktif gamma, isotop 137Cs, penukar kation, zeolit Lampung dan container. MANUCFACTURING OF 137Cs GAMMA RAY SOURCE WITH ACTIVITY 20 mCi FROM PEB U3Si2-Al POST IRRADIATION IN STAINLESS STEEL CONTAINER. In the post-irradiation examination of fuel element plate (PEB) U3Si2-Al), a solution of high activity as a result of testing nuclear fuel stored in hotcell with enough volume. The solution can not be discarded as waste because it still contains fission isotop such as137Cs, uranium and transuranium, which has a long half life and dangerous for the environment. This can help the industry in order to fulfill the needs of a radioactive source in Indonesia, because until now 137Cs isotope is derived from foreign industries. In addition, the procurement and transportation of isotopes 137Cs require stringent requirements, because they have toget permission from the National Nuclear Energy Agency (BAPETEN), thus causing the price of high activity 137Cs isotopes becomes expensive to Indonesia. For these reasons, BATAN as nuclear R&D institutions in Indonesia need to study make isotopes 137Cs gamma radiation source, which is contained in the waste from spent fuel test results U3Si2-Al. Isotope 137Cs can be used very widely, such as in the analysis of environmental samples, the oil and gas industry, construction, radiography, fisheries, hospitals, and mining. Making isotope 137Cs gamma radiation source starting from the collection of waste from the test results PEB U3Si2- Al. Waste solution was collected in a bottle with volume 65 mL. Collection of 137Cs isotopes of other fission carried out using the method of cation exchange with weight 45 gr of zeolite Lampung. The results of separation are 137Cs-zeolite in the solid phase and the other isotopes are in the liquid phase. 137Cs-zeolite solid is then dried and then weighed and measured its activity using a spectrometer-g. Result of analisys by spectrometer-g was obtained acitivity of 137Cs-zeolite solids was 20 mCi.137Cs-zeolite solids then packed in sealed containers (shield source) capsule-shaped stainless steel and than certificate by PTKMR-BATAN.Keywords: Process wastle of PEB U3Si2-Al, gamma radioactive, isotope 137Cs, cation exchange, zeolite Lampung and container.

Finger injury from over-exposure to an industrial gamma radiation source

Burns ◽  
2015 ◽  
Vol 41 (2) ◽  
pp. e8-e10 ◽  
Author(s):  
Cihan Sahin ◽  
Ceyhun Cesur ◽  
Celalettin Sever ◽  
Fikret Eren
Keyword(s):  
Gamma Radiation ◽  
Radiation Source ◽  
Finger Injury

scholarly journals Impact of Cobalt-60 Gamma Radiation Source on Electronic Devices using Geant4

2017 ◽  
Vol 105 ◽  
pp. 40-45
Author(s):  
Abd. Hafiz Zakaria ◽  
Yasir M. Mustafah ◽  
Jaafar Abdullah ◽  
Nahrul Khair ◽  
Hanafi Ithnin
Keyword(s):  
Gamma Radiation ◽  
Radiation Source ◽  
Electronic Devices

scholarly journals Estudo das variações da massa específica em Pinus oocarpa através da técnica de atenuação da radiação gama

FLORESTA ◽  
1999 ◽  
Vol 29 (12) ◽  
Author(s):  
MARCOS ANTONIO DE REZENDE ◽  
ELIAS TAYLOR DURGANTE SEVERO ◽  
ISABEL ROYUELA QUINTANA
Keyword(s):  
Gamma Radiation ◽  
Physical Properties ◽  
Radiation Source ◽  
Nuclear Energy ◽  
Annual Rings ◽  
Specific Mass ◽  
Pinus Oocarpa ◽  
Radiation Technique ◽  
In The Beginning

O trabalho enfatiza as vantagens em se usar técnica da radiação gama no estudo das propriedades físicas da madeira, evidenciando o uso do Amerício–241. Com essa técnica foram estudados os anéis de crescimento de sete árvores de Pinus oocarpa aos 24 anos, fundamentado nas variações de sua massa específica como indicativos de qualidade da madeira para fins industriais e energéticos. Os resultados mostraram que a maioria das árvores apresentaram um pico de alta massa específica no início do crescimento, seguida de um decréscimo até a idade de 4 anos. A partir dessa idade, houve um acréscimo gradual da massa específica até a idade de corte, efetuada aos 24 anos. Observou-se ainda uma grande variabilidade entre a massa específica do lenho inicial e tardio durante todo período de crescimento destas árvores. Os valores encontrados para a média da massa específica, em g/cm3, do Pinus oocarpa, nas posições relativas à altura comercial da árvore (base, 25%, 50% e 75%), foram respectivamente de: 0,58; 0,56; 0,52 e 0,53, evidenciando um decréscimo da massa específica no sentido base-topo das árvores. Specific mass variations study in Pinus oocarpa by the gamma radiation lessening technique Abstract The work emphasizes the advantages in using nuclear energy as the gamma radiation technique in the studies of the physical properties of the wood, evidencing the use of the 241 Am, as gamma radiation source. Through that technique, the annual rings of seven Pinus oocarpa were analyzed, being studied the variations of the specific mass as a factor of quality. The results showed that the most of the trees of Pinus oocarpa presented a pick of high specific mass in the beginning of the growth, followed by a decrease on the 4 year-old. Starting from that age, there was gradual increment of the specific mass to the cut age, made to the 24 years. The values find to the average specific mass, g/cm3, in the commercial height (base, 25%, 50% e 75%) were respectively 0,58; 0,56; 0,52 e 0,53, showing a decrease in the specific mass (base-top direction) of the trees.

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