Results 161 to 170 of about 2,762 (182)

RAST-AI: A Standalone Nodal Diffusion/Deep Neural Network Code for Reactor Analysis and Simulation

International Conference on Physics of Reactors 2022 (PHYSOR 2022), 2022
Siarhei Dzianisau, Fathurrahman Setiawan, Korawit Saeju, Jinsu Park, Deokjung Lee   +4 more
openaire   +1 more source

Analytic Error Analysis of Cross Section Interpolation Methods in Nodal Diffusion Codes-II: Numerical Results

International Conference on Physics of Reactors 2022 (PHYSOR 2022), 2022
Thomas Folk, Siddhartha Srivastava, Dean Price, Brendan Kochunas, Krishna Garikipati   +4 more
openaire   +1 more source

Verification of Adjoint Solution Commutativity with the New OpenNode Nodal Diffusion Code

Nuclear Science and Engineering
Hicham Satti, Otman El Hajjaji, Tarek El Bardouni, Tarik El Ghalbzouri   +3 more
openaire   +1 more source

Variational nodal method for three-dimensional multigroup neutron diffusion equation based on arbitrary triangular prism

Annals of Nuclear Energy, 2021
Xiaobin Tang, Kun Zhuang, Sipeng Wang
exaly  

Description of the two-dimensional nodal codes "NRMS," a multigroup static code, and "NRMT," a one- and two-group transient code for solution of the neutron diffusion equation in rectangular geometry

1977
"August 1977." ; Series statement handwritten on spine ; Includes bibliographical ...
openaire   +1 more source

Static modeling of core flowering scenarios in SFRs with nodal diffusion code DYN3D

2023
Nikitin, E., Fridman, E.
openaire   +1 more source

Microscopic depletion with the correction of microscopic cross sections in nodal diffusion code DYN3D

2016
Bilodid, Y., Kotlyar, D., Shwageraus, E., Fridman, E., Kliem, S.   +4 more
openaire   +2 more sources

Cervical Nodal Metastases of Unknown Origin

Ca-A Cancer Journal for Clinicians, 1971
E W Strong
exaly  

Development of a high order and multi-dimensional nodal code, ACNEC3D, for reactor core analysis

Annals of Nuclear Energy, 2013
Abdolhamid Minuchehr, N Poursalehi, A Zolfaghari   +2 more
exaly  

Preliminary Full-Core Analysis of Nuclear Thermal Propulsion Reactors Using Nodal Diffusion Codes

Nuclear and Emerging Technologies for Space (NETS 2024)
Jake Smith, Dan Kotlyar
openaire   +1 more source