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

Author(s):  
Aslina Br. Ginting ◽  
Yanlinastuti Yanlinastuti ◽  
Noviarty Noviarty ◽  
Boybul Boybul ◽  
Arif Nogroho ◽  
...  

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.

Author(s):  
Yohanes Yohanes ◽  
◽  
Muhammad Heriansyah ◽  

Friction welding is a type of solid state welding where the welding process is carried out in a solid phase to combine various types of ferrous and non-ferrous metals that cannot be welded by the fusion welding method but for welding different metals the welding results are less than optimal due to cracks on the surface of the welding results and differences in mechanical properties that cause the welding result to be brittle, therefore an interlayer is used. In this study, observations were made on the process and results of the joint friction welding using dissimilar metal material between mild steel ST37 and stainless steel 201 with copper interlayer. The results of the test will be a tensile test to see the maximum tensile strength and a hardness test to see the hardness value of the interlayer variation of 0.3 mm, 0.5 mm, 1 mm and without an interlayer. The conclusions obtained are: (1) The effect of the addition of an interlayer on the rotary friction welding process includes the friction phase, the forging phase and the results of welding parameters in the form of motor power, motor angular speed, the change in specimen length is greater without using an interlayer compared to using an interlayer while the duration of welding time is greater using an interlayer than without using an interlayer. (2) The maximum tensile test results were obtained at the 1 mm interlayer at 482.43 MPa and the maximum hardness test results obtained at the 1 mm interlayer were 321.34 VHN.


2014 ◽  
Vol 641-642 ◽  
pp. 427-433
Author(s):  
Shuang Cheng ◽  
Feng Lin ◽  
Pei Long Yang ◽  
Pei Ke Zhu ◽  
Jin Gen Deng ◽  
...  

This paper analyzed the corrosion environment of Missan oilfields and investigated the oilfield country tubular goods used in other similar oilfields. Summarized the effect of partial pressure ratio of H2S/CO2 and Cl-to the corrosion behavior of OCTG. This paper concluded the service condition, test results and anti-corrosion mechanism of carbon steel, low-chrome steel, modified martensitic stainless steel and nickel alloy. Finally arrived at conclusion that the nickel alloy can meet the requirement of Missan oilfields, some literature reported that the modified martensitic stainless steel can apply in H2S/CO2 environment. In the condition that be easy to replace the tubular, carbon steel and low-chrome steel tubular can meet the requirement with corrosion inhibitor.


Author(s):  
Jean Alain Le Duff ◽  
Andre´ Lefranc¸ois ◽  
Jean Philippe Vernot

In February/March 2007, The NRC issued Regulatory Guide “RG1.207” and Argonne National Laboratory issued NUREG/CR-6909 that is now applicable in the US for evaluations of PWR environmental effects in fatigue analyses of new reactor components. In order to assess the conservativeness of the application of this NUREG report, Low Cycle Fatigue (LCF) tests were performed by AREVA NP on austenitic stainless steel specimens in a PWR environment. The selected material exhibits in air environment a fatigue behavior consistent with the ANL reference “air” mean curve, as published in NUREG/CR-6909. LCF tests in a PWR environment were performed at various strain amplitude levels (± 0.6% or ± 0.3%) for two loading conditions corresponding to a simple or to a complex strain rate history. The simple loading condition is a fully reverse triangle signal (for comparison purposes with tests performed by other laboratories with the same loading conditions) and the complex signal simulates the strain variation for an actual typical PWR thermal transient. In addition, two various surface finish conditions were tested: polished and ground. This paper presents the comparisons of penalty factors, as observed experimentally, with penalty factors evaluated using ANL formulations (considering the strain integral method for complex loading), and on the other, the comparison of the actual fatigue life of the specimen with the fatigue life predicted through the NUREG report application. For the two strain amplitudes of ± 0.6% and ± 0.3%, LCF tests results obtained on austenitic stainless steel specimens in PWR environment with triangle waveforms at constant low strain rates give “Fen” penalty factors close to those estimated using the ANL formulation (NUREG/6909). However, for the lower strain amplitude level and a triangle loading signal, the ANL formulation is pessimistic compared to the AREVA NP test results obtained for polished specimens. Finally, it was observed that constant amplitude LCF test results obtained on ground specimens under complex loading simulating an actual sequence of a cold and hot thermal shock exhibits lower combined environmental and surface finish effects when compared to the penalty factors estimated on the basis of the ANL formulations. It appears that the application of the NUREG/CR-6909 in conjunction with the Fen model proposed by ANL for austenitic stainless steel provides excessive margins, whereas the current ASME approach seems sufficient to cover significant environmental effects for representative loadings and surface finish conditions of reactor components.


2009 ◽  
Vol 55 (3) ◽  
pp. 454-462 ◽  
Author(s):  
Allan J Barnes ◽  
Bruno S De Martinis ◽  
David A Gorelick ◽  
Robert S Goodwin ◽  
Erin A Kolbrich ◽  
...  

Abstract Background: Understanding the excretion of 3,4-methylenedioxymethamphetamine (MDMA) and metabolites in sweat is vital for interpretation of sweat tests in drug treatment, criminal justice, and workplace programs. Methods: Placebo, low (1.0 mg/kg), and high (1.6 mg/kg) doses of oral MDMA were given double-blind in random order to healthy volunteers (n = 15) with histories of MDMA use. Participants resided on the closed clinical research unit for up to 7 days after each dose. Volunteers wore PharmChek® sweat patches (n = 640) before, during, and after controlled dosing. Patches were analyzed by solid phase extraction and GC-MS for MDMA, methylenedioxyamphetamine (MDA), 4-hydroxy-3-methoxyamphetamine (HMA), and 4-hydroxy-3-methoxymethamphetamine (HMMA). Limits of quantification (LOQ) were 2.5 ng/patch for MDMA and 5 ng/patch for HMA, HMMA, and MDA. Results: MDMA was the primary analyte detected in 382 patches (59.7%), with concentrations up to 3007 ng/patch. MDA was detected in 188 patches (29.4%) at <172 ng/patch, whereas no HMMA or HMA was detected; 224 patches (35.0%) and 60 patches (9.4%) were positive for MDMA and MDA, respectively, at the 25-ng/patch threshold proposed by the Substance Abuse and Mental Health Services Administration. Conclusions: Sweat testing was shown to be an effective and reliable method for monitoring MDMA use in this controlled MDMA administration study. However, variability in sweat excretion suggests that results should be interpreted qualitatively rather than quantitatively. These data provide a scientific database for interpretation of MDMA sweat test results.


1983 ◽  
Vol 4 (2P2) ◽  
pp. 681-686 ◽  
Author(s):  
G. R. Longhurst ◽  
G. A. Deis ◽  
P. Y. Hsu ◽  
L. G. Miller ◽  
R. A. Causey

2013 ◽  
Vol 690-693 ◽  
pp. 2371-2378
Author(s):  
Wei Pu Xu ◽  
Yi Ting Liu

A brief overview is given in the conventional domed bursting disc structure and manufacturing method. 316L stainless steel as a template is selected. With the investigation on bursting disc material tensile test method, the test results are summarized,also the burst results of disc burst pressure in different sizes. With the help of bursting disc material performance test and bursting disc burst pressure test of 316L , the test results provide a reference for other types of bursting disc.


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