Neutron transport - Wikipedia
Neutron transport (also known as neutronics) is the study of the motions and interactions of neutrons with materials. Nuclear scientists and engineers often need to know where neutrons are in an apparatus, in what direction they are going, and how quickly they are moving.
Neutronics - an overview | ScienceDirect Topics
3.1 Neutronics. The neutron population in a nuclear reactor is a function of time, position, direction of motion, and energy. Neutrons appear at some position in the reactor as a result of a fission reaction between uranium or plutonium and a neutron from a previous generation.
Neutronics Calculation Advances at Los Alamos: Manhattan …
We briefly summarize early simpler and more approximate neutronics methods and then describe the need to better predict neutronics behavior through consideration of theoretical equations, models and algorithms, experimental measurements, and available computing capabilities and …
Advanced modeling and simulation of neutronic and thermal …
Taking advantage of recent advances in computer science, MIT researchers have developed new methods that dramatically accelerate the solution of the equations describing neutron transport—characterization of the movements made by neutrons in time and space from the moment the first atom of nuclear fuel undergoes fission—as well as fluid flow and...
Neutronic Analysis - an overview | ScienceDirect Topics
The neutronics plays a key role in estimating core reactivity and temperature distributions in fuel, clad, and coolant. Since fast reactors mostly use liquid metal coolants, the operational aspects require more insight.
Neutronics of Advanced Nuclear Systems | SpringerLink
This book provides a systematic and comprehensive introduction to the neutronics of advanced nuclear systems, covering all key aspects, from the fundamental theories and methodologies to a wide range of advanced nuclear system designs and experiments.
Neutronics - an overview | ScienceDirect Topics
Neutronics is defined as the analysis of neutron transport and decay chains, which is crucial for fuel performance modeling. It involves calculating heat generation, power distribution, and decay heat in rods during irradiation and storage.
Fusion Neutronics - SpringerLink
The book focuses on the neutronic characteristics of fusion systems and introduces a series of theories and methodologies that were developed to address the challenges of fusion neutronics. Further, it introduces readers to the unique principles and procedures of neutronics design, experimental methodologies and methodologies for fusion systems.
Neutronics of Advanced Nuclear Systems - ResearchGate
2019年1月1日 · This book provides a systematic and comprehensive introduction to the neutronics of advanced nuclear systems, covering all key aspects, from the fundamental theories and methodologies to a wide...
PROTEUS - Argonne National Laboratory
PROTEUS encompasses the set of advanced neutronics modeling and simulation tools developed at Argonne including cross section generation codes, transport solvers, and mesh generation tools. The PROTEUS toolset has been used to study numerous reactor types ranging from small thermal test reactors to large sodium cooled fast reactors.