Zobrazeno 1 - 10
of 43
pro vyhledávání: '"Micheal A. Smith"'
Publikováno v:
International Journal of Sports Physical Therapy, Vol 19, Iss 7 (2024)
# Introduction Adductor-related groin pain involves an injury to the common aponeurosis connecting the rectus abdominus and adductor longus to the pubis. It commonly occurs in sports that require cutting and pivoting and can result in significant lo
Externí odkaz:
https://doaj.org/article/f6077419ffa4484aa77b00e827d5dea2
Autor:
Yunzhao Li, Micheal A. Smith, Yongping Wang, Tengfei Zhang, Elmer E Lewis, Hongchun Wu, Won Sik Yang
Publikováno v:
Nuclear Science and Engineering. 193:652-662
The Generalized Partitioned Matrix (GPM) acceleration method for the Variational Nodal Method (VNM) with diffusion approximation is presented. In the GPM method, the vectors of expansion coefficien...
Publikováno v:
EPJ Web of Conferences, Vol 247, p 10030 (2021)
The DIF3D code (DIFfusion 3D) has been a workhorse of fast reactor analysis work at Argonne National Laboratory for over 40 years. DIF3D was primarily built in the late 1970s as a three-dimensional multigroup diffusion equation solver operating on se
Autor:
E. R. Shemon, C. H. Lee, Jun Fang, Ronald Rahaman, Dillon Shaver, T. Fei, Yeon Sang Jung, Micheal A. Smith, B. Feng
Publikováno v:
EPJ Web of Conferences, Vol 247, p 06026 (2021)
The goal of this work was to calculate the impact of the delayed neutron precursor drift in fast spectrum Molten Salt Reactors (MSRs) using coupled solutions from the neutronics code PROTEUS and the computational fluid dynamics code Nek5000. Specific
Publikováno v:
Annals of Nuclear Energy. 112:225-235
In thermal reactor physics fine mesh neutron diffusion calculations in which homogenization is only at the pin cell level are of considerable interest. However, the slow convergence of iterations on fine-mesh spatial grids limits their applicability
Autor:
Andrew A. Allerman, Luke Yates, Robert Kaplar, Andrew T. Binder, Micheal L. Smith, Mary H. Crawford, Jeff Steinfeldt, Vincent M. Abate, Andrew M. Armstrong, Jeramy R. Dickerson
Publikováno v:
ECS Meeting Abstracts. :1003-1003
Publikováno v:
Annals of Nuclear Energy. 159:108323
As part of the Versatile Test Reactor (VTR) program, extensive validation work is being performed to demonstrate the fidelity of the Argonne Reactor Code (ARC) software package presently used for the core design studies. It is anticipated that this s
Publikováno v:
Nuclear Science and Engineering. 188:160-174
A three-dimensional variational nodal method (VNM) is presented for pressurized water reactor core calculations without fuel-moderator homogenization. The nodal functional is presented and ...