Jumat, 08 Juli 2011

THE EXPERT SYSTEM FOR INDUSTRIAL RADIOGRAPH EVALUATION WITH IMAGE ENHANCEMENT


THE EXPERT SYSTEM FOR INDUSTRIAL RADIOGRAPH EVALUATION WITH IMAGE ENHANCEMENT

Bagus Tri Atmoyo, Djoko Marjanto, Supriyono
Sekolah Tinggi Teknologi Nuklir - Badan Tenaga Nuklir Nasional
Jl. Babarsari Kotak Pos 6101/YKBB Yogyakarta
bagustriatmoyo@gmail.com

ABSTRACT
The Radiograph Evaluation Expert System called REES has material data and radiograph data as input. Material data contains shape, welding technique and dimension (thickness and diameter) of the material. Radiograph data contains parameters of defect indication like shape, intensity, location, direction, distribution, continuity, and also thickness. The data are used as premise to select the rule to construct the conclusion. The conclusion contains information about defect appearance and kind of its, material acceptance, the cause and the solution. The radiograph data collecting process can be helped by image enhancement feature in the REES with digitization process of radiograph. Image enhancement feature contains brightness, contrast, saturation and exposure enhancement; histogram equalization; gray scale transformation; inverse intensity; convulsion and edge detection using Sobel or Roberts filters. The testing of REES used digital radiograph image courtesy of IIW as evaluation’s object. The image that had been actualizing with image enhancement feature show a defect indication with length shape, dark (low intensity) and located in root of the weld. Data processed by inference machine and found the conclusion informs that defect had been found. The defect is Incomplete Penetration. According to acceptance criteria of ASME VIII Division 2 – Alternative Rule, the material must be rejected and for remedial actions take apart the weld and do re-welding process to the material as the solution for this result.
Keyword: Expert System, Radiograph, Defect, Image Enhancement

PROGRAM SIMULASI PERHITUNGAN POPULASI FLUKS NEUTRON DALAM TERAS REAKTOR NUKLIR


PROGRAM SIMULASI PERHITUNGAN POPULASI FLUKS NEUTRON
DALAM TERAS REAKTOR NUKLIR

SIMULATION PROGRAM FOR CALCULATING THE POPULATION OF NUTRON FLUX
 IN THE NUCLEAR REACTOR CORE

Bagus Tri Atmoyo1, Syarip2, Supriyono1
1Sekolah Tinggi Teknologi Nuklir-Badan Tenaga Nuklir Nasional
2Pusat Teknologi Akselerator dan Proses Bahan-Badan tenaga Nuklir Nasional
Jl. Babarsari Kotak Pos 6101/YKBB Yogyakarta
Email : bagustriatmoyo@gmail.com


ABSTRAK

Program simulasi perhitungan fluks neutron dalam teras reaktor nuklir memiliki input berupa fraksi neutron kasip (β), konstanta peluruhan (λ), reaktivitas (ρ), umur satu generasi neutron (l ) dan waktu (t). Data tersebut diolah untuk menyusun suatu persamaan karakteristik guna memperoleh akar-akar persamaan karakteristik (wj) dan residu (Aj). wj dan Aj digunakan dalam membentuk persamaan populasi fluks neutron terhadap fungsi waktu (nt/n0). Output dari program ini berupa populasi fluks neutron terhadap fungsi waktu yang ditampilkan dalam bentuk angka maupun grafik. Pengujian dilakukan salah satunya dengan memasukkan data β dan λ dari isotop U235, ρ dan l masing-masing sebesar 0,002 dan  0,001 s. Hasil pengujian menunjukkan nilai nt/n0 saat t = 0 s sebesar 0,07088 dan mengalami peningkatan yang signifikan saat t = 55 s menjadi 1,31444 dan saat t = 150 s menjadi 167,21324. Hal ini sesuai dengan pernyataan bahwa bila ρ > 0 maka grafik populasi fluks neutron terhadap waktu cenderung menjauhi nol.

Kata Kunci : Simulasi, Reaktivitas, Persamaan Karakteristik, Fluks Neutron, Fungsi Waktu.

ABSTRACT

Simulation program for calculating the neutron flux in the nuclear reactor core have input in form of delayed neutron fraction (β), the decay constant (λ), reactivity (ρ), the age of a generation of neutron (l ) and time (t). The data is processed to construct a characteristic equation to obtain its roots (wj) and residue (Aj). ωj and Aj are used in forming the population of neutron flux equation versus a function of time (nt/n0). The output of this program is a population of neutron flux to the function of the time displayed whether graphs or numbers or both. One of the test performed by entering the β and λ from the U235 isotope, ρ and l shown as 0.003 and 0.0001 s respectively. The test result show the value at t = 0 s, nt/n0 = 0.07088 and increase significantly at t = 55 s become 1.31444 and at t = 150 s become 167,21324. This is consistent with the statement that if ρ > 0 then the graph of the population of neutron flux equation versus a function of time tends to away from zero.

Keywords : Simulation, Reactivity, Characteristic Equation, Neutron Flux, Function of Time.