نتایج جستجو برای: mcnp design
تعداد نتایج: 960935 فیلتر نتایج به سال:
The structure of a 150 MeV neutron data le is outlined. Emphasis is put on the possibility to process a high-energy le with NJOY into an MCNPlibrary. Examples of parts of such a le are given as illustration. Furthermore, we have processed some existing data libraries and report on the encountered di culties. Accordingly, we give recommendations for the format to be used for evaluated neutron da...
در این رساله عملکرد یک موتور توربوپراپ که ملخ آن از نوع clark y 5868-r9 است در شرایط نقطه طرح (on- design) و خارج از نقطه طرح (off- design) مورد مطالعه قرار گرفته شده است. موتور توربوپراپ یکی از انواع موتور جت در تراست بالا و مصرف مخصوص سوخت پایین است که عدد ماخ پروازی آن هرگز از 8/. تجاوز نمی کند. دور موتور های توربوجت به حدی زیاداست که در صورت اتصال مستقیم به ملخ، سرعت نوک تیغه های ملخ به سرع...
BACKGROUND High-molecular-weight phthalates, such as diisononyl phthalate (DINP) and diisodecyl phthalate (DIDP), are used primarily as polyvinyl chloride plasticizers. OBJECTIVES We assessed exposure to DINP and DIDP in a representative sample of persons ≥ 6 years of age in the U.S. general population from the 2005-2006 National Health and Nutrition Examination Survey (NHANES). METHODS We ...
This paper demonstrates the applicability of Monte Carlo analysis to perform nuclear reactor core simulations with thermofluid feedback from a computational fluid dynamics code. An interface program, McSTAR, was written to couple MCNP5 to the commercial computational fluid dynamics code STAR-CD. McStar is a Perl script which alternately executes MCNP5, STAR-CD and cross section update routines ...
The 250kW TRIGA Mark II research reactor, Vienna, is equipped with experimental facilities inside and outside the reactor core. Outside the core, there are four beam tubes (three radial and one tangential beam tube), a thermal column and a neutron radiography collimator, supplying neutrons for irradiation experiments. These experiments include neutron radiography, neutron tomography, neutron ac...
Modern technical computing environments, such as Mathematica or Matlab, provide powerful tools and techniques for research reactor analysis combined with advanced graphical user interfaces. In addition, reactor calculations can now be efficiently supported by neutronics codes based on the Monte Carlo method due to the dramatic increase of computer performance in recent years. In particular for ...
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...
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