Results 111 to 120 of about 25,004 (172)

Neutron Instruments for Research in Coordination Chemistry. [PDF]

Eur J Inorg Chem
Xue ZL, Ramirez-Cuesta AJ, Brown CM, Calder S, Cao H, Chakoumakos BC, Daemen LL, Huq A, Kolesnikov AI, Mamontov E, Podlesnyak AA, Wang X.   +11 more
europepmc   +1 more source

Bi-Continuous W-Rich Refractory High Entropy Alloy-Cu Composite: Toward Material Innovation of Nuclear Reactor Coolant System. [PDF]

Small Methods
Yoon KN, Kim IH, Kim JY, Hosemann P, Park ES.   +4 more
europepmc   +1 more source

Concept design overview: a question of choices and compromise. [PDF]

Philos Trans A Math Phys Eng Sci
Waldon C, Muldrew SI, Keep J, Verhoeven R, Thompson T, Kisbey-Ascott M.   +5 more
europepmc   +1 more source

Synthesizing nuclear power plant fouling with fractal characteristics enables an in-depth study of concerned nuclear safety issues. [PDF]

iScience
Liu Y, Liu X, He H, Zhang T, Chai X.
europepmc   +1 more source

Overview of the Properties and Formation Process of Interface Traps in MOS and Linear Bipolar Devices. [PDF]

Micromachines (Basel)
Ren Y, Zhu M, Dai X, Li L, Liu M.
europepmc   +1 more source

Some of the next articles are maybe not open access.

Related searches:

Stochastic Theory of Neutron Transport in Nuclear Reactor

Journal of Computational and Theoretical Transport, 2021
The work is an extended version of the report presented at the conference ICTT-26. In the Part I we derive the forward and backward time-dependent linear stochastic equations for probability densit...
R. Y. Nesterenko
openaire   +2 more sources

A Robust, Relaxation–Free Multiphysics Iteration Scheme for CMFD–Accelerated Neutron Transport k–Eigenvalue Calculations–I: Theory

Nuclear science and engineering, 2021
This paper presents a new robust scheme for coupled physics nuclear reactor calculations. We focus specifically on high-fidelity whole-core transport calculations with coarse mesh finite difference (CMFD) coupled to thermal hydraulics.
Qicang Shen, B. Kochunas
semanticscholar   +1 more source

A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, 2022
The variational nodal method (VNM) is an advanced nodal method in the field of reactor physics. The VNM solves neutron transport equations directly without transverse leakage interpolations used in other nodal methods.
Qizheng Sun, Tengfei Zhang, Xiaojing Liu, Xiang Chai, Jinbiao Xiong   +4 more
semanticscholar   +1 more source

Development of Uncertainty Analysis Techniques for the Fission Matrix–Based Neutron Transport Code RAPID

Nuclear science and engineering, 2022
The combined fission matrix (CFM) method is a newly developed neutron transport theory. This method estimates the fission matrix of the reactor core or spent fuel pool by combining a set of database fission matrices.
D. He, W. Walters
semanticscholar   +1 more source