Elliott Biondo

Elliott Biondo
Oak Ridge National Laboratory | ORNL · Reactor and Nuclear Systems Division

Ph.D.

About

18
Publications
666
Reads
How we measure 'reads'
A 'read' is counted each time someone views a publication summary (such as the title, abstract, and list of authors), clicks on a figure, or views or downloads the full-text. Learn more
47
Citations
Citations since 2016
11 Research Items
35 Citations
201620172018201920202021202201234567
201620172018201920202021202201234567
201620172018201920202021202201234567
201620172018201920202021202201234567

Publications

Publications (18)
Article
In fusion energy systems (FES) high-energy neutrons born from burning plasma activate system components to form radionuclides. The biological dose rate that results from photons emitted by these radionuclides after shutdown—the shutdown dose rate (SDR)—must be quantified for maintenance planning. This can be done using the Rigorous Two-Step (R2S) m...
Article
In fusion energy systems (FES) neutrons born from burning plasma activate system components. The photon dose rate after shutdown from resulting radionuclides must be quantified. This shutdown dose rate (SDR) is calculated by coupling neutron transport, activation analysis, and photon transport. The size, complexity, and attenuating configuration of...
Conference Paper
In fusion energy systems (FES) neutrons born from burning plasma activate system components. The photon dose rate after shutdown from resulting radionuclides must be quantified. This shutdown dose rate (SDR) is calculated by coupling neutron transport, activation analysis, and photon transport. The size, complexity, and attenuating configuration of...
Article
Monte Carlo (MC) shielding calculations often use weight windows (WWs) and biased sources formed from a deterministic estimate of the adjoint flux to improve the convergence rate of tallies. This requires a significant amount of computer memory, which can limit the memory available for high-resolution tally output. A new method is proposed for redu...
Conference Paper
For effective GPU-based Monte Carlo transport simulations, algorithms must be optimized with respect to the single-instruction multiple-thread (SIMT) paradigm. Commonly used free gas elastic scattering algorithms, such as Doppler-broadening rejection correction (DBRC) involve rejection sampling with low sampling efficiency, leading to GPU thread di...
Article
Many spatially complex fission, fusion, and national security Monte Carlo (MC) radiation transport scenarios involve combining computer-aided design (CAD) models with constructive solid geometry (CSG) models. A layered geometry method has been implemented in the Shift MC code to address this need. With layered geometry, multiple CAD and/or CSG mode...
Conference Paper
Constructive solid geometry (CSG) has traditionally been sufficient for Monte Carlo (MC) neutron transport simulations of standard light-water reactors (LWRs). Advanced reactor designs, as well as demand for multiphysics coupling and ex-core analysis, have created opportunities to use computer-aided design (CAD) to model a subset of reactor compone...
Conference Paper
The Transformational Challenge Reactor design effort in 2021 included constructing a full-core mock-up of the reactor in-core components. This effort was undertaken to ascertain differences between the as-designed and as-built individual components and determine impacts of assembly of the as-built components into a full-scale core assembly. Through...
Article
The GPU solver within the Shift continuous-energy Monte Carlo neutron transport code has been extended to provide domain decomposition in addition to domain replication to enable the solution of problems with memory requirements exceeding the capacity of a single GPU. The strategy follows the Multiple Set, Overlapping Domain (MSOD) approach that is...
Technical Report
Full-text available
This manual provides instructions for using the Omnibus front end to the Exnihilo code suite, which contains the Denovo and Shift transport solvers.
Article
The standard Monte Carlo (MC) k-eigenvalue algorithm involves iteratively converging the fission source distribution using a series of potentially time-consuming inactive cycles before quantities of interest can be tallied. One strategy for reducing the computational time requirements of these inactive cycles is the Sourcerer method, in which a det...
Conference Paper
The Shift Monte Carlo code has been integrated into the TRITON sequence to enable flexible, scalable depletion calculations, and a few-group cross section generation capability has been added to Shift. The new TRITON depletion capability was tested using simple pressurized water reactor (PWR) and boiling water reactor (BWR) problems to verify that...
Conference Paper
Detailed radiation transport calculations are necessary for many aspects of the design of fusion energy systems (FES) such as ensuring occupational safety, assessing the activation of system components for waste disposal, and maintaining cryogenic temperatures within superconducting magnets. Hybrid Monte Carlo (MC)/deterministic techniques are nece...

Network

Cited By

Projects