Shemon et al., 2023 - Google Patents
Development and Porting of Nuclear Reactor Computational Models for the NRIC Virtual Test Bed in FY23Shemon et al., 2023
View PDF- Document ID
- 2039641185643486542
- Author
- Shemon E
- Abdelhameed A
- Chaube A
- Fang J
- Fei T
- Hua T
- Lee C
- Novak A
- Ooi Z
- Shaver D
- Stauff N
- Wozniak N
- Zou L
- Publication year
External Links
Snippet
The US DOE's National Reactor Innovation Center (NRIC) hosts an open-source website and associated GitHub repository called the Virtual Test Bed (VTB) on which computational models for advanced reactors are documented and shared with the reactor community. In …
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/40—Other aspects relating to nuclear fission
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/38—Fuel
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/34—Fast breeder reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING; COUNTING
- G06F—ELECTRICAL DIGITAL DATA PROCESSING
- G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
- G06F17/50—Computer-aided design
- G06F17/5009—Computer-aided design using simulation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
- G21D2003/002—Core design; Core simulations
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2004/00—SOLUTION
- G21Y2004/30—Improving a design
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/201—Inadequate efficiency
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Kotlyar et al. | Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system | |
| Mikityuk et al. | FAST: An advanced code system for fast reactor transient analysis | |
| Stauff et al. | Core design of the holos-quad microreactor | |
| Stauff et al. | Detailed analyses of a triso-fueled microreactor: Modeling of a micro-reactor system using neams tools | |
| Zhou et al. | 3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM | |
| Alzaben et al. | Core neutronics and safety characteristics of a boron-free core for Small Modular Reactors | |
| Renfro et al. | Preliminary Evaluation of Alternate Designs for HFIR Low-Enriched Uranium Fuel | |
| Walker et al. | SCALE modeling of the fast spectrum heat pipe reactor | |
| Lee et al. | Micro reactor simulation using the PROTEUS suite in FY19 | |
| Stauff et al. | Multiphysics analysis of load following and safety transients for MicroReactors | |
| Shaver et al. | Initial industry collaborations of the center of excellence | |
| Design space exploration for salt cooled reactor systems | ||
| Matthews et al. | Task 1: evaluation of M&S tools for micro-reactor concepts | |
| Gorton et al. | Assessment of CASL VERA for BWR analysis and application to accident tolerant SiC/SiC channel box | |
| Shemon et al. | Development and Porting of Nuclear Reactor Computational Models for the NRIC Virtual Test Bed in FY23 | |
| Terlizzi et al. | Sodium-cooled fast reactor reference plant model | |
| Fanning et al. | Multi-resolution modeling of subassembly pin bundles for advanced fast reactor safety simulations | |
| Shemon et al. | Applications of SHARP Toolkit to SFR Challenging Problems: Evaluation of Hot Channel Factors and Demonstration of Zooming Capability | |
| Gentry et al. | Development and performance simulations of the MPACT-AGREE code coupling interface for MAGNOX reactors | |
| Choi et al. | Development and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis | |
| Downar et al. | Science based nuclear energy systems enabled by advanced modeling and simulation at the extreme scale | |
| Abdellatif | Experimental Validation of Single-phase Natural Circulation Loop to Support the Development of Molten Salt Reactors | |
| Imron et al. | Pressurized water reactor mixed Oxide/UO2 transient benchmark calculations using Monte Carlo Serpent 2 code and open nodal core simulator ADPRES | |
| He et al. | Assessment of transient characteristics of fast reactors and influences of minor actinides using neutron transport method | |
| Hu et al. | FY20 SAM code developments and validations for transient safety analysis of advanced non-LWRs |