Results 31 to 40 of about 12,472 (163)

Simulation and Comparative Study of Interaction Between Ray and Medium in Borehole Based on FLUKA Software

Cejing jishu
In nuclear logging, Monte Carlo simulation method is widely employed across various stages from instrument development and design to data interpretation.
LIU Juntao, LI Wenxin, MARINA R. ABDELNOUR, TIAN Heng, WANG Yiwei, GAO Yuan, LIU Zhiyi   +6 more
doaj   +1 more source

Solution of neutron-transport multigroup equations system in subcritical systems [PDF]

Nuclear Energy and Technology, 2018
An iteration method has been implemented to solve a neutron transport equation in a multigroup diffusion approximation. A thermoelectric generator containing plutonium dioxide, used as a source of thermal and electric power in spacecraft, was studied.
Igor V. Shamanin, Sergey V. Bedenko, Vladimir N. Nesterov, Igor O. Lutsik, Anatoly A. Prets   +4 more
doaj   +3 more sources

Time-resolved secondary triton burnup 14 MeV neutron measurement by a new scintillating fiber detector in middle total neutron emission ranges in deuterium large helical device plasma experiments

AAPPS Bulletin, 2021
A middle-sensitivity scintillating fiber detector (hereafter middle Sci-Fi detector) that works at a deuterium-tritium neutron flux of ~105-107 cm−2s−1 was utilized to measure secondary deuterium-tritium neutron emission rates with high temporal ...
K. Ogawa, M. Isobe, S. Sangaroon, E. Takada, T. Nakada, S. Murakami, J. Jo, G. Q. Zhong, Yipo Zhang, S. Tamaki, I. Murata   +10 more
doaj   +1 more source

Energy-dependent and Energy-integrated Two-moment General-relativistic Neutrino Transport Simulations of a Hypermassive Neutron Star

The Astrophysical Journal
We compare two-moment-based energy-dependent and three variants of energy-integrated neutrino transport general-relativistic magnetohydrodynamics simulations of a hypermassive neutron star. To study the impacts due to the choice of the neutrino transport
Patrick Chi-Kit Cheong, Francois Foucart, Matthew D. Duez, Arthur Offermans, Nishad Muhammed, Pavan Chawhan   +5 more
doaj   +1 more source

Design and Application of DG-FEM Basis Functions for Neutron Transport on Two-Dimensional and Three-Dimensional Hexagonal Meshes

Journal of Nuclear Engineering
Reactor design requires safety studies to ensure that the reactors will behave appropriately under incidental or accidental situations. Safety studies often involve multiphysics simulations where several branches of reactor physics are necessary to model
Ansar Calloo, David Labeurthre, Romain Le Tellier   +2 more
doaj   +1 more source

Diffusion Approximation to Neutron Transport Equation with First Kind of Chebyshev Polynomials

Süleyman Demirel Üniversitesi Fen-Edebiyat Fakültesi Fen Dergisi, 2015
: The first kind of Chebyshev polynomials are used for the series expansion of the neutron angular flux in neutron transport theory. The first order approximation known as the diffusion approximation is applied to one-dimensional neutron transport ...
Ökkeş EGE, Hakan ÖZTÜRK, Ahmet BÜLBÜL   +2 more
doaj  

MCNP Simulation of NaI Detector for PGNAA Technology

Journal of Isotopes
Sodium iodide (NaI) detector has wide applications in Prompt Gamma-ray Neutron Activation Analysis (PGNAA) due to its excellent detection efficiency and relatively low cost.
Zeliang WANG, Wenbao JIA, Xiaoyan YANG, Zhenhua ZHANG, Yan ZHANG, Can CHENG   +5 more
doaj   +1 more source

The intensive DT neutron generator of TU Dresden

EPJ Web of Conferences, 2018
TU Dresden operates an accelerator-based intensive DT neutron generator. Experimental activities comprise investigation into material activation and decay, neutron and photon transport in matter and R&D work on radiation detectors for harsh environments.
Klix Axel, DÖring Toralf, Domula Alexander, Zuber Kai   +3 more
doaj   +1 more source

Monte Carlo Simulation of NE213 Response to 241Am-Be Neutrons Using the PTRAC Card of the MCNPX Code and the Light Transport Code PHOTRACK [PDF]

مجله علوم و فنون هسته‌ای, 2013
The response of an NE213 scintillator to Am-Be neutrons, in which the neutron and neutron-induced charged particles transports have been undertaken, has been simulated with the use of MCNPX’ PTRAC card whilst the scintillation light transport has been ...
M Tajik, N Ghal Eh, G. R Etaati, H Afarideh   +3 more
doaj  

NECP-MCX software simulation of AB-BNCT neutron transport process

He jishu
BackgroundBoron neutron capture therapy (BNCT) is a highly promising and precise cancer treatment technique with substantial application prospects worldwide. The neutron transport process directly influences beam characteristics and accuracy of treatment
HU Zhen, ZHANG Lu, ZHOU Yifu, HE Qingming, GU Long, ZHANG Shixu   +5 more
doaj   +1 more source