نتایج جستجو برای: mcnp calculation
تعداد نتایج: 102713 فیلتر نتایج به سال:
Abstract Monte Carlo N-Particle (MCNP) is a widely-used code in nuclear engineering, but it needs high computation times due to the tracking of every single particle and interaction event. This causes shielding optimization using trial-and-error take long complete. It can be solved by multiprocessing, this requires MCNP source which difficult obtain. Therefore, paper aims suggest solution on ho...
monte carlo method is a very accurate method to optimize medical diagnostic radiology spectra and simulation of radiation transportation. using mcnp code, radiology and mammography attenuated x-rayspectraweresimulated.the ipem report number 78 was used as a reference to compare with the geant4 and mcnp simulations because of its popularity and wide availability. the results of geant4 in 40kev s...
Although the Monte Carlo method is considered to be the most accurate method available for solving radiation transport problems, its applicability is limited by its computational expense. Thus, biasing techniques, which require intuition, guesswork, and iterations involving manual adjustments, are employed to make reactor shielding calculations feasible. To overcome this difficulty, we have dev...
The number of Positron Emission Tomography (PET) centers has been growing rapidly. Many of the new facilities have been retrofitted into existing imaging centers and hospitals. Space in the facilities is often cramped, resulting in the hot lab, patient quiet rooms, and the scanners frequently being placed in close proximity to uncontrolled areas where non-occupational dose limits apply. Of part...
The Boron Neutron Capture Therapy (BNCT) treatment planning process of the Harvard/MIT team used for their clinical Phase I trials is very time consuming. If BNCT proves to be a successful treatment, this process must be made more efficient. Since the Monte Carlo treatment planning calculations were the most time consuming aspect of the treatment planning process, requiring more than thirty six...
The leakage neutron spectrum measurements have been done on benchmark spherical assembly-nickel sphere with a diameter of 50 cm and copper cube (block) dimensions 49.5 x 48 cm3 in Research Centre Rez (RC Rez). 252Cf source was placed into the centre nickel cube. proton recoil method used for measurement using hydrogen proportional detectors (HPD) pressure 400 1000 kPa (diameter is 4 cm) scintil...
introduction: average glandular dose calculation in mammography with mo-rh target-filter and dose calculation for different situations is accurate and fast. material and methods: in this research, first of all, x-ray spectra of a mo target bombarded by a 28 kev electron beam with and without a rh filter were calculated using the mcnp code. then, we used the sobol-wu parameters to write a fortra...
Background and purpose: Concave eye applicators of Ru-106, a beta emitter source, have a lot of use in brachytherapy of intraocular tumors. This has led to the need of knowing the exact dose distribution caused by beta radiation to the tumor and its normal surrounding tissue. The purpose of this study was the 3D calculation of dose distribution for three Ru-106 plaques: CCA, CCB, and CGD in a h...
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