Results 51 to 60 of about 788 (153)
APPLICATION OF MCNP FOR PREDICTING POWER EXCURSION DURING LOCA IN ATUCHA-2 PHWR
This thesis consists in the developing and application of a methodology based on MCNP code to predict power and reactivity excursions depending on different representation of physical variables.
PECCHIA, MARCO
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ABSTRACT Copper (Cu) and copper‐based alloys are indispensable in high‐heat‐flux systems, such as aerospace propulsion, fusion reactors, and advanced power electronics, due to their high thermal conductivity and good manufacturability. However, extreme service conditions increasingly demand not only high thermal conductivity but also elevated ...
Yicheng Cao +8 more
wiley +1 more source
Boron‐10 carriers and their applications in boron neutron capture therapy
Summary of different types of boron drugs. Abstract Boron neutron capture therapy (BNCT) has emerged as a promising therapeutic modality in cancer treatment, demonstrating the ability to selectively eliminate cancer cells through the 10B(n,α)7Li nuclear reaction with minimal side effects on normal tissues.
Dachao Tang +7 more
wiley +1 more source
In analyzing the power density distribution within the core of a nuclear reactor, it is necessary to employ numerical methods to solve the neutron transport equation and obtain the neutron flux density distribution.
LIU Haopo, LI Yunzhao, WU Hongchun, CAO Liangzhi
doaj +1 more source
Dehydrogenation Thermodynamic and Kinetic Challenges of Mg‐Ni‐Based Alloy Hydrides
ABSTRACT Solid‐state hydrogen storage stands as a pivotal, safe, and efficient solution for the future hydrogen economy. Among diverse hydrogen storage systems, Mg‐Ni‐based alloy hydrides are recognized as cornerstone materials. However, their practical application is hindered by two core challenges: the high thermodynamic stability of the hydride ...
Jinglan He +6 more
wiley +1 more source
A multi-region collision probability method for determining neutron spectra and reaction rates
textThe collision probability approach to neutron transport can be used to obtain the energy-dependent neutron spectrum in nuclear reactor systems as well as other quantities of interest.
Dembia, Christopher Lee
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Nuclear Reactor Physics and Operation: Neutronic Analysis for Nuclear Reactor Design
This book serves as a thorough reference for students, researchers, and professionals in nuclear engineering and reactor physics, offering a detailed exploration of the core principles behind nuclear reactor theory, neutron transport, neutronic analysis,
Lomonaco, Guglielmo +2 more
core +1 more source
Calculation of Lambda modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method [PDF]
[EN] The method explained in this paper solves the steady-state of the neutron transport equation for 1D and 2D systems modeled with Cartesian geometry, by using the Discrete Ordinates method SN for the angular discretization and the Finite Difference ...
Miró Herrero, Rafael +4 more
core +1 more source
Why LA‐ICPMS Fission‐Track Age Data Are So Dispersed? A Pseudo‐EDM Solution
Abstract Fission track (FT) dating is a well‐established thermochronological technique widely used to reconstruct rocks' thermal histories. Over the past two decades, development of Laser Ablation Inductively Coupled Plasma Mass Spectrometry (LA‐ICPMS) has significantly advanced the application of FT dating by enabling rapid measurements of uranium ...
Yuntao Tian, Huixia Zhong
wiley +1 more source
A Complex-Geometry Validation Experiment for Advanced Neutron Transport Codes [PDF]
The Idaho National Laboratory (INL) has initiated a focused effort to upgrade legacy computational reactor physics software tools and protocols used for support of core fuel management and experiment management in the Advanced Test Reactor (ATR) and its ...
Skerjanc, William F. +6 more
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