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NINE LLC, located in the North Caroline Research Triangle, is a spinoff of the North Carolina State University. NINE LLC mission is to provide to nuclear power and other industries high quality research, innovative solutions and analytical services in support of design and of safe and economic operation.

NINE LLC staff includes NCSU professors and graduates and other experienced and internationally acclaimed professionals.

NINE LLC will target as customer power plant vendors, engineering-architect companies, plant operators, and the government.

NINE LLC focuses on development, assessment and application of complex deterministic and probabilistic models for simulation of operation and accidents in support of design, licensing and operations. Cutting edge methods, developed in academia, in multi-physics approach to technological and safety problems will be tested, adapted and applied to current industrial problems. The services include also independent validation of analytical methods, assessment of their accuracy and applications. The services are performed following internationally recognized standards.

Specifically in the field of nuclear safety, thanks to the experience of its member and collaborators NINE-LLC is able to provide advanced services including: System, Containment Thermal Hydraulics, Reactor Physics, and Fuel Performance analyses. The deep knowledge of the mentioned disciplines can be adopted for the deployment of different kind of services ranging from the safety assessment of a nuclear installation; to the support for a licensing application being capable to contribute and/or review different SAR chapters (e.g. 4, 15, 16 and 19 NUREG 0800); to the assessment of NPP response in case of postulated Severe Accident including source term evaluation.  

NINE-LLC licensing support service includes applications compliant with US NRC regulations including recent updates (e.g. 10 CFR 50.46c). NINE-LLC can assist a licensee in the development of Evaluation Models (EM), qualification and application of Best Estimate Plus Uncertainty (BEPU) method. Also, conservative EMs can be supported. Suitable methodologies have been developed to meet both customer and regulators requirements in these fields.

NINE LLC offers experimental support for design of power and other industrial facilities and development and assessment of analytical models.  This includes experiment planning, experimental facility construction and operation, conduct and evaluation of experiments.


COMPETENCES

REACTOR PHYSICS

  • ALTS Methodology for cross sections generation and modeling for Transient applications
  • NEM Core Nodal Diffusion and SP3 Simulator for staedy state and atrsnient applications
  • MCOR - Monte Carlo based steady state and deplition calculation
  • Scale based methodology for propagation of nuclear data uncertainty
  • Iterative Transport Diffusion Methology (ITDM) for Next Generation High Fidelity Core Analysis Tools
  • Methodology for optimum mulit-group and few-group energy selection for different reactor designs
  • Methodology for implementation of resonance upscatering effects in cross-section generation

CORE THERMAL-HYDRAULIC ANALYSIS

  • Development and Maintenance of CTF and CTFFuel Code
  • Methodology for High (CFD) to Low (CTF) Model Information for Spacer Grid Applications
  • Methodology and Interface for coupling Core Thermal-Hydraulics (CTF) to System Thermal-Hydraulics
  • Methodology for Uncertainty Quantification of Core Thermal-Hydraulics Code using statistical Methods

IN-CORE FUEL MANAGMENT

  • GARCO: Methodology and Software for Loading pattern and burnable poisons placement in PWR and VVER using Genetic Algorithms
  • Methodology for Fuel Assembly design optimization for Small Modular Reactors (SMRs)
  • Methodology and Software for Fuel Cycle cost evaluation
  • Methodology for multi-cycle loading pattern and burnable poison optimization

ADVANCED REACTOR DESIGNS

  • Design and Safety Analysis and Evaluation of Small Modular Reactors
  • Design and Safety Analysis and Evaluation of High Temperature Reactors/Prismatic and Pebble Bed
  • Design and Safety Analysis and Evaluation of Fast Liquid Cooled Reactors
  • Design and Safety Analysis and Evaluation of Molten Salt Reactors

MULTIPHYSICS CODE AND METHODOLOGIES DEVELOPMENT AND APPLICATIONS

  • Multi-Physics Methodologies and Codes for LWR Design and Safety Assessment
  • Multi-Physics Methodologies and Codes for HTR Design and Safety Assessment
  • Multi-Physics Methodologies and Codes for Fast Liquid Reactors Design and Safety Assessment
  • Open-Foam based Multi-Physics Methodologies and Codes for Molten Salt Reactors
  • Development of Hierarchical Multi-Physics V&V Methodology
  • Uncertainty Quantification and Propagation for Multi-Physics applications

BIG DATA, DATA ANALYTICS AND ARTIFICIAL INTELLIGENCY FOR NUCLEAR ENGINEERING APPLICATIONS

  • Core and Experimental Design
  • Model Development and Validation
  • Characterization and Optimization of Test Conditions in test/research reactors
  • Optimization of Operating and Safety Margins in Operating and Advanced Nuclear Plants
  • Management and Control Systems for different types of reactors