Structural design of stainless steel members — comparison between Eurocode 3, Part 1.4 and test results

2000 ◽  
Vol 54 (1) ◽  
pp. 51-73 ◽  
Author(s):  
B.A. Burgan ◽  
N.R. Baddoo ◽  
K.A. Gilsenan
Keyword(s):  
Stainless Steel ◽  
Structural Design ◽  
Test Results ◽  
Steel Members ◽  
Eurocode 3

Experimental results for structural design of Wire-and-Arc Additive Manufactured stainless steel members

2020 ◽  
Vol 167 ◽  
pp. 105858 ◽  
Author(s):  
Vittoria Laghi ◽  
Michele Palermo ◽  
Giada Gasparini ◽  
Valentina Alena Girelli ◽  
Tomaso Trombetti
Keyword(s):  
Stainless Steel ◽  
Structural Design ◽  
Experimental Results ◽  
Steel Members

Investigation on Material Selection in Missan Oilfields Similar Environment

2014 ◽  
Vol 641-642 ◽  
pp. 427-433
Author(s):  
Shuang Cheng ◽  
Feng Lin ◽  
Pei Long Yang ◽  
Pei Ke Zhu ◽  
Jin Gen Deng ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Carbon Steel ◽  
Nickel Alloy ◽  
Martensitic Stainless Steel ◽  
Material Selection ◽  
Pressure Ratio ◽  
Service Condition ◽  
Corrosion Mechanism ◽  
Test Results ◽  
Chrome Steel

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.

Effects of Surface Finish and Loading Conditions on the Low Cycle Fatigue Behavior of Austenitic Stainless Steel in PWR Environment for Various Strain Amplitude Levels

2009 ◽  
Author(s):  
Jean Alain Le Duff ◽  
Andre´ Lefranc¸ois ◽  
Jean Philippe Vernot
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Strain Amplitude ◽  
Surface Finish ◽  
Low Cycle Fatigue ◽  
Fatigue Behavior ◽  
Complex Loading ◽  
Loading Conditions ◽  
Test Results ◽  
Cycle Fatigue

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.

Study on Conventional Domed Bursting Disc Material and Burst Pressure Test

2013 ◽  
Vol 690-693 ◽  
pp. 2371-2378
Author(s):  
Wei Pu Xu ◽  
Yi Ting Liu
Keyword(s):  
Stainless Steel ◽  
Tensile Test ◽  
316L Stainless Steel ◽  
Performance Test ◽  
Test Method ◽  
Burst Pressure ◽  
Test Results ◽  
Manufacturing Method ◽  
Pressure Test ◽  
Disc Material

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.

scholarly journals Study on Suitability and Behaviour of Ferrocement in Folded Plates

2021 ◽  
Vol 9 (VI) ◽  
pp. 3540-3546
Author(s):  
Mr. V. Karthick
Keyword(s):  
Stainless Steel ◽  
Compressive Strength ◽  
Cross Section ◽  
Test Results ◽  
Logical Investigation ◽  
Second Stage ◽  
Concrete Application ◽  
Extended Range ◽  
Properties Of Materials ◽  
Low Consumption

Ferro concrete is one of the developments arising material an alternative for the traditional RCC in numerous viewpoints. Ferro concrete is the fate of the minimal expense houses and precast houses. Folded plates are answer for the more extended range rooftops in prudent and aesthetical manner. This project consolidates the upsides of both Ferro concrete and collapsed plate. The box type Ferro concrete collapsed plates of size 0.6 m x 1.80 m x 0.15 m are casted by thinking about various diaries and RCC collapsed plates in thought while fixing dimensions. In first period of trial various properties of materials utilized for projecting are tried and compressive strength of the mortar utilized is tried, the test is done at 1:2 of concrete: sand proportion and 0.35 water concrete ratio. In second stage the example is casted with Stainless Steel cross section of 2 mm opening is utilized and 2 layers on front and posteriors of 6mm width 150m divided skeleton steel is laid. The projected examples is tried for 28 days strength in stacking outline and the outcomes are contrasted and logical investigation Using ANSYS for load versus redirection and reasonableness of Ferro concrete application in collapsed plates are studies. The test results are shown acceptable outcomes, at last with low consumption and low self-weight Ferro concrete constructions are acceptable substitute for RCC.

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.

scholarly journals ANALISYS OF THE INFLUENCE OF GLUE JOINTS ON THE MEASUREMENT OF PHYSICAL PROPERTIES OF STRUCTURAL ELEMENTS USING FIBER BRAGG GRATING

2020 ◽  
Vol 10 (3) ◽  
pp. 99-102
Author(s):  
Tomasz Zieliński ◽  
Łukasz Zychowicz
Keyword(s):  
Stainless Steel ◽  
Physical Properties ◽  
Fiber Bragg Grating ◽  
Transmission Spectrum ◽  
Measuring Transducer ◽  
Bragg Grating ◽  
Transmission Characteristic ◽  
Test Results ◽  
Structural Elements ◽  
Factors Affecting

The research presents the analysis of the influence of the glue connection on the measurement of elongation of stainless steel and aluminum samples by means of fiber Bragg grating (FBG) with uniform fibers used as a measuring transducer. Research indicates two possible factors affecting the deformation of the transmission spectrum obtained during elongation measurement. One of them is the type of adhesive that is used to make the connection between the fiber Bragg grating and the tested sample. The second possible factor is method of connection's execution. The need for research on glue connection resulted from the formation of defects mainly in the form of numerous side bands visible in the transmission spectrum during the measurement of elongations. The test results were presented in the form of graphs obtained on the basis of transmission characteristic.

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