نتایج جستجو برای: mcnp

تعداد نتایج: 925  

Journal: :journal of biomedical physics and engineering 0
m m firoozabadi university of birjand gh izadi vasafi k karimi-sh university of birjand m ghorbani

background: in neutron interaction with matter and reduction of neutron energy due to multiple scatterings to the thermal energy range, increasing the probability of thermal neutron capture by neutron captures makes dose enhancement in the tumors loaded with these materials.   objective: the purpose of this study is to evaluate dose distribution in the presence of  10 b ,  157 gd  and  33 s  ne...

Journal: :iranian journal of medical physics 0
taha eidi shahid beheshti university, faculty of nuclear engineering, radiation-medicine department, tehran, iran

introduction pterygium is a wing-shaped, vascular, fleshy growth that originates from the conjunctiva and can spread into the corneal limbus and beyond. beta irradiation after bare sclera surgery of primary pterygium is a simple, effective, and safe treatment, which reduces the risk of local recurrence. materials and methods dosimetric components of strontium-90 (90sr), phosphorous-32 (32p), an...

Journal: :journal of paramedical sciences 0
jamal amiri faculty of paramedicine, science, ilam university of medical science, ilam, iran seyed pezhman shirmardi nuclear science and technology research institute (nstri), tehran, iran rohollah adeli nuclear science and technology research institute (nstri), tehran, iran mostafa erfani nuclear science and technology research institute (nstri), tehran, iran elham saniei faculty of physics, amirkabir university of technology, tehran, iran reza vafaee proteomics research center, shahid beheshti university of medical sciences, tehran, iran

chlorotoxin is a 36 amino acids peptide, which is able to block chloride channels isolated from mouse brain. a derivative of chlorotoxin is synthesized and it is labeled by iodine 131; then animal experiments carry out on rats. multiple organ doses may be calculated with biological distribution results in rats with labeled compounds using simulated mcnp4c code. human dose can be calculated usin...

Journal: :iranian journal of radiation research 0
d. rezaei ochbelagh department of physics, university of mohageg ardebily, ardebil, iran h. miri hakimabad department of physics, faculty of sciences, ferdowsi university of mashhad, mashhad, iran r. izadi najafabadi department of physics, faculty of sciences, ferdowsi university of mashhad, mashhad, iran

background: several landmine detection methods, based on nuclear techniques, have been suggested during the recent years. neutron energy moderation, neutron-induced gamma emission, neutron and gamma attenuation, and fast neutron backscattering are nuclear-based methods used for landmine detection. the aim of this study is to use backscattered neutron for landmine detection. materials and method...

Journal: :iranian journal of radiation research 0
a. mostaar medical physics department, tehran university of medical sciences, tehran, iran m. allahverdi department of radiotherapy physics, cancer institute, tehran, iran m. shahriari gamma irradiation center, atomic energy organization of iran, tehran, iran

background: in treating patients with radiation, the degree of accuracy for the delivery of tumor dose is recommended to be within ± 5% by icru in report 24. the experimental studies have shown that the presence of low-density inhomogeneity in areas such as the lung can lead to a greater than 30% change in the water dose data. therefore, inhomogeneity corrections should be used in treatment pla...

پایان نامه :وزارت علوم، تحقیقات و فناوری - دانشگاه صنعتی اصفهان - دانشکده فیزیک 1388

ضرایب انباشت داده های مهمی در مسئله ی حفاظ سازی در مقابل تابش های هسته ای از جمله تابش گاما هستند که پاسخ آشکارساز به فوتون های بدون برخورد را تصحیح می کنند. دانستن ضریب انباشت برای مواد مختلف و ترکیبات آن ها از اهمیت زیادی برخوردار است. در این پایان نامه ابتدا ضریب انباشت پرتودهی تابش گاما برای حفاظ کروی دو لایه ای ساخته شده از آب و سرب که ضخامت کل حفاظ بین mfp2 تا mfp10 تغییر می کرد با استفاد...

2007
D. V. Fedorchenko

Design and maintenance of nuclear cycle facilities mandatory imply implementation of efficient radiation protection. Radiation environment assessment and shielding optimization require a considerable amount of numerical calculations. Nowadays mathematical modelling methods and corresponding software are widely used for such kind of problems. All the software used for radiation fields modelling ...

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