Results 91 to 100 of about 10,040 (154)
CRISPR/Cas9, while transformative, faces challenges in specificity, precision, delivery, accessibility, flexibility, and safety. This review addresses these limitations by highlighting strategies to reduce off‐target effects, exploring HDR‐based and alternative editing approaches, and evaluating advanced delivery mechanisms.
Muna Alariqi +8 more
wiley +1 more source
In nuclear logging, Monte Carlo simulation method is widely employed across various stages from instrument development and design to data interpretation.
LIU Juntao +6 more
doaj +1 more source
Neutronics Studies on the NIST Reactor Using the GA LEU fuel [PDF]
The National Bureau of Standards Reactor (NBSR) located on the National Institute of Standards and Technology (NIST) Gaithersburg campus, is currently underway of fuel conversion from high enriched uranium (HEU) fuel to low enriched uranium (LEU) fuel ...
Britton, Kyle A
core +1 more source
A graphical user interface for Monte Carlo dose calculations for brachytherapy with egs_brachy
Abstract Background Recent advancements in brachytherapy necessitate precise dose calculations, transitioning from the traditional TG43 planning methods to the more sophisticated TG186 recommendations. However, the availability of accessible and efficient Monte Carlo (MC) codes capable of interfacing with clinical data for these advanced calculations ...
Narjes Moghadam +7 more
wiley +1 more source
A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor
We present a new model, developed with the Serpent Monte Carlo code, for neutronics simulation of the TRIGA Mark II reactor of Pavia (Italy). The complete 3D geometry of the reactor core is implemented with high accuracy and detail, exploiting all the ...
Boarin, Sara +9 more
core +1 more source
Out‐of‐field neutron radiation from clinical proton, helium, carbon, and oxygen ion beams
Abstract Background In hadron therapy, out‐of‐field doses, which may in the long‐term cause secondary cancers, are mostly due to neutrons. Very recently, 4He and 16O beams have been added to protons and 12C ions for clinical therapy. Purpose The focus of this article is to compare secondary neutron doses produced by clinical protons, 4He, 12C, and 16O ...
Matteo Bolzonella +11 more
wiley +1 more source
COMPTEL neutron response at 17 MeV [PDF]
The Compton imaging telescope (COMPTEL) instrument of the Gamma Ray Observatory was exposed to 17 MeV d,t neutrons prior to launch. These data were analyzed and compared with Monte Carlo calculations using the MCNP(LANL) code.
Ait-Ouamer, Farid +5 more
core +1 more source
MCNP - a general Monte Carlo code for neutron and photon transport [PDF]
MCNP is a very general Monte Carlo neutron-photon transport code with approximately 250 person years of Group X-6 code development invested. It is highly portable, user-oriented, and a true production code as it is used about 60 Cray hours per month by about 150 Los Alamos users.
Forster, R. A., Godfrey, T. N. K.
openaire +1 more source
Design of portable shield for neutron sources using MCNP Computer Code [PDF]
In this work a proposed design of portable shield for neutron sources was performed theoretically using MCNP5 code. The shield is composed of three layers; lead layer for gamma attenuation, PMMA (Poly-methyl methacrylate) layer for fast neutron thermalization and a layer of B2O3 for thermal neutron absorption.
openaire +1 more source
Reactor Core Design and Analysis for a Micronuclear Power Source
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 ...
Hao Sun +5 more
doaj +1 more source

