نتایج جستجو برای: mcnp simulation code

تعداد نتایج: 704198  

Journal: :Processes 2023

The goal of this study was to evaluate the impact simulating different fuel shapes for material testing reactor (MTR). Two OpenMC codes were built, and first model simulated using a curved shape element mimic real dimensions MTR. code core parameters validated with collected from experimental work two well-known Monte Carlo simulation (MCNP SCALE). validation process included axial flux profile...

2018
Hao Sun Chenglong Wang Xiao Liu Wenxi Tian Suizheng Qiu Guanghui Su

Underwater vehicle is designed to ensure the security of country sea boundary, providing harsh requirements for its power system design. Conventional power sources, such as battery and Stirling engine, are featured with low power and short lifetime. Micronuclear reactor power source featured with higher power density and longer lifetime would strongly meet the demands of unmanned underwater veh...

Journal: :Epj Web of Conferences 2021

Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is critical input to the design and validation many aspects reactor design, including, shielding, material lifetime remote maintenance requirements/scheduling. Neutronics studies, which perform in-depth analysis are typically performed using transport codes such as MCNP, TRIPOLI, Serpent, FLUKA OpenMC....

A. Karimian, A. Rahmim, M.N.  Nasrabadi, N. Ahmadi,

Background: In CT systems, the machine utilizes a bowtie filter to shape the X-ray beam and remove lower energy photons. The shape of this bowtie filter is complicated and its geometry is often not available in detail. These renders the CT dose index (CTDI) to have different values in measurement versus Monte Carlo simulation studies and other analytical calculations especially in dosimetry of ...

Journal: :IOP conference series 2022

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...

2004
Mauro N. Takeda Mauro S. Dias Marina F. Koskinas

The methodology for simulating all detection processes in a 4πβ − γ coincidence system by means of the Monte Carlo technique is described. The goal is to predict the behavior of the observed activity as a function of the 4πβ detector efficiency. In this approach, the information contained in the decay scheme is used for determining the contribution of all radiations emitted by the selected radi...

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