نتایج جستجو برای: کد mcnpx 260

تعداد نتایج: 18495  

Journal: :Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine 2014
Jaroslav Solc Petr Kovar Jiri Suran Virginia Peyres Eduardo García-Toraño

A novel free release measurement facility (FRMF) was developed within the joint research project "Metrology for Radioactive Waste Management" of the European Metrology Research Programme. Before and during FRMF design and construction, Monte Carlo calculations with MCNPX and PENELOPE codes were used to optimize the thickness of the shielding, the dimensions of the container, and the shape of de...

2013
Tianyu Liu Xining Du Wei Ji George Xu

This paper describes the development of a Graphics Processing Unit (GPU) accelerated Monte Carlo photon transport code, ARCHERGPU, to perform CT imaging dose calculations with good accuracy and performance. The code simulates interactions of photons with heterogeneous materials. It contains a detailed CT scanner model and a family of patient phantoms. Several techniques are used to optimize the...

2007
J. J. Bergman

The need for more accurate radiation therapy treatment planning is driving improvements in radiation transport calculations. In particular, the inclusion of patient specific anatomy and tissue density heterogeneities will be very important, particularly for treatment modalities that involve strong material discontinuities. The study presented here compares the application of the deterministic c...

2007
PW Chin JP Giddy DG Lewis DW Walker

We present a computing framework for Monte Carlo simulation of radiation transport. In conformity with our belief that Monte Carlo studies should be anchored to physics but not to any particular code, we have enabled different Monte Carlo codes in this environment. The framework embraces the EGSnrc family, FLUKA, MCNP/MCNPX, GEANT4 and PENELOPE; dedicated and non-dedicated resources; shared and...

2007
S. D. Clarke S. A. Pozzi E. Padovani T. J. Downar Shaun D. Clarke Sara A. Pozzi

The most recent release of photonuclear interaction data for Monte Carlo applications is the ENDF/B-VII library. While this current version offers several improvements over its predecessors, it does not address the observed, sometimes quite significant variance in the measured data. For instance, for U, the cross-section data in the ENDF/B-VII library is consistently larger than all measurement...

Journal: :journal of biomedical physics and engineering 0
m khadem abolfazli babol medical university s r mahdavi iran medical university m mahdavi mazandaran universityسازمان اصلی تایید شده: دانشگاه علوم پزشکی بابل (babol university of medical sciences) gh ataei babol medical universityسازمان اصلی تایید شده: دانشگاه علوم پزشکی ایران (iran university of medical sciences)

background: gold nanoparticles are emerging as promising agents for cancer therapy and are being investigated as drug carriers, photothermal agents, contrast agents and radiosensitisers. objective: the aim of this study is to understand characteristics of secondary electrons generated from interaction of gold nanoparticles gnps with x-rays as a function of nanoparticle size and beam energy and ...

ژورنال: سنجش و ایمنی پرتو 2017

One of the main characteristics of heavy water research reactors is their high production of plutonium. This work demonstrates the possibility of reduction of plutonium production and other actinides in heavy water research reactors. Among the many ways for reducing plutonium production in a heavy water reactor, in this research, changing the fuel from natural uranium to thorium-uranium mixed f...

ژورنال: سنجش و ایمنی پرتو 2015

Many detection methods have been applied to detect radon gas. Due to the low noise and high resolution of gas detectors compared to semiconductor detectors or scintillation detectors, using them to detect alpha radiation is very considerable. Microstrip proportional detector is also included in this group and it has not been used for the detection of radon. In this article, response of the micr...

در این پژوهش از روش (1/v Poisoning Method ) یا روش اختلال برای محاسبه پارامترهای سینتیکی راکتور تحقیقاتی تهران مانند ضریب تکثیر مؤثر (Keff)، کسر موثر نوترون‌های تأخیری eff)β(، عمر نوترون (ℓ) استفاده شده است. هدف از این پژوهش این است که میزان خطای به وجود آمده در مقادیر این پارامتر ها مخصوصأ عمر نوترون(ℓ) که ابتدا توسط کد MCNPX محاسبه شده است کاهش یافته و عدد منطقی تری به دست آورده شود. اساس کار...

با توسعه فناوری هسته ای در دنیا و استفاد از این تکنولوژی در صنعت و مراکز درمانی، توجه کشورها به این مقوله و سرمایه گذاری در این حوزه بیشتر شده است. به دلیل وجود تابش های هسته ای همچون گاما و نوترون و از طرفی مضر بودن اینگونه پرتوها برای سلامت انسان ها، در این نوع مراکز برای جلوگیری از آثار جبران ناپذیر این نوع پرتوها باید حفاظ هایی ساخته شود تا علاوه بر کاهش انرژی و شدت این نوع تابش ها، صرفه اق...

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