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Paul K. Romano
Researcher at Argonne National Laboratory
Publications - 69
Citations - 2789
Paul K. Romano is an academic researcher from Argonne National Laboratory. The author has contributed to research in topics: Monte Carlo method & Neutron transport. The author has an hindex of 14, co-authored 58 publications receiving 1752 citations. Previous affiliations of Paul K. Romano include Massachusetts Institute of Technology.
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Journal ArticleDOI
ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data
David Brown,Mark B. Chadwick,Roberto Capote,A.C. Kahler,Andrej Trkov,M.W. Herman,A. A. Sonzogni,Yaron Danon,Allan D. Carlson,Michael E Dunn,D.L. Smith,Gerald M. Hale,Goran Arbanas,R. Arcilla,C.R. Bates,B. Beck,B. Becker,Forrest B. Brown,R.J. Casperson,Jeremy Lloyd Conlin,D.E. Cullen,M.-A. Descalle,Richard B. Firestone,T. Gaines,Klaus H Guber,Ayman I. Hawari,Jesse C. Holmes,Timothy Johnson,Toshihiko Kawano,Brian C. Kiedrowski,Arjan J. Koning,Stefan Kopecky,Luiz Leal,John Lestone,C.R. Lubitz,J.I. Márquez Damián,Caleb Mattoon,E. A. McCutchan,Said F. Mughabghab,Petr Navrátil,Denise Neudecker,Gustavo Nobre,Gilles Noguere,Mark W. Paris,Marco T. Pigni,A. J. M. Plompen,Boris Pritychenko,V.G. Pronyaev,D. Roubtsov,D. Rochman,Paul K. Romano,Peter Schillebeeckx,Stanislav Simakov,M. Sin,I. Sirakov,Brad W. Sleaford,Vladimir Sobes,E.S. Soukhovitskii,Ionel Stetcu,Patrick Talou,Ian J. Thompson,S. C. van der Marck,L. Welser-Sherrill,Dorothea Wiarda,Morgan C. White,J.L. Wormald,R.Q. Wright,M.L. Zerkle,G. Žerovnik,Y. Zhu +69 more
TL;DR: The new ENDF/B-VIII.0 evaluated nuclear reaction data library as mentioned in this paper includes improved thermal neutron scattering data and uses new evaluated data from the CIELO project for neutron reactions on 1 H, 16 O, 56 Fe, 235 U, 238 U and 239 Pu described in companion papers.
Journal ArticleDOI
OpenMC: A state-of-the-art Monte Carlo code for research and development
TL;DR: An overview of OpenMC, an open source Monte Carlo particle transport code recently developed at the Massachusetts Institute of Technology, which uses continuous-energy cross sections and a constructive solid geometry representation, enabling high-fidelity modeling of nuclear reactors and other systems.
Journal ArticleDOI
The OpenMC Monte Carlo particle transport code
Paul K. Romano,Benoit Forget +1 more
TL;DR: The present work describes the methods used in the OpenMC code and demonstrates the performance and accuracy of the code on a variety of problems.
The OpenMC Monte Carlo particle transport code
Paul K. Romano,Benoit Forget +1 more
TL;DR: OpenMC as discussed by the authors is a Monte Carlo code for simulation on high-performance computing platforms, which is developed from scratch with a focus on high performance scalable algorithms as well as modern software design practices.
Journal ArticleDOI
Development of burnup methods and capabilities in Monte Carlo code RMC
TL;DR: Burnup cases including a PWR pin and a 5 × 5 assembly group are calculated, thereby demonstrating the burnup capabilities of the RMC code and the computational time and memory requirements of RMC are compared with other MC burnup codes.