Prashant Jain

Prashant K Jain

Section Head, Advanced Reactor Engineering & Development, Nuclear Energy and Fuel Cycle Division

Contact

865.574.6272 | JAINPK@ORNL.GOV

All Publications

Assessing the Heat Transfer Modeling Capabilities of CFD Software for Involute-Shaped Plate Research Reactors

Driving Economics and Reducing Risks: The Business Case for Security-by-Design in Nuclear Power

COMSOL Results for the Nominal Steady-State Operation of the Proposed 95-MW LEU Silicide Core for HFIR Conversion

Experimental and computational characterization of a modified Sioutas Cascade impactor for respirable radioactive aerosols

Oak Ridge National Laboratory's Strategic Research and Development Insights for Digital Twins

Material selection and manufacturing for high-temperature heat exchangers: Review of state-of-the-art development, opportunities, and challenges

High Flux Isotope Reactor Low-Enriched Uranium Conversion Overview

Advanced manufacturing and digital twin technology for nuclear energy

Novel designs for ejector-based systems for enhanced fluid recovery verified through CFD Simulations

Fuel Conversion Efforts at the High Flux Isotope Reactor – a 2023 Status Update

Thermomechanical analysis and modeling of involute-shaped fuel plates using the Cheverton–Kelley experiments for the High Flux Isotope Reactor

Air Ingress and DLOFC Studies in Scaled HTGR Geometry Using Additively Manufactured TCR Fuel Elements

Technical Challenges and Gaps in Integration of Advanced Sensors, Instrumentation, and Communication Technologies with Digital Twins for Nuclear Application

Security by Design: A Plant Design and Component Based Approach to Technical Solutions to Insider and Outsider Threat.

Digital Twins for Nuclear Power Plants and Facilities

Conceptual Design of the Transformational Challenge Reactor...

Coolant Channel Design for Additively Manufactured Reactor Cores

UPDATES FROM THE INVOLUTE WORKING GROUP

Transformational Challenge Reactor Design Characteristics

A Large Eddy Simulation Study of Flow Turbulence, Alumina Transport, and Bath Temperature Evolution in Conventional Aluminum-Smelting Cell Using OpenFOAM

CFD Modeling for the Transformational Challenge Reactor Preliminary Design

IMPLEMENTATION OF THE ENERGY EQUATION SOLVER TO THE LATTICE BOLTZMANN METHOD-BASED CODE PRATHAM

ADDITIVELY MANUFACTURED SURFACE HEAT TRANSFER ENHANCEMENTS FOR THE TRANSFORMATIONAL CHALLENGE REACTOR

Experimental investigation on the coolability of nuclear reactor debris beds using seawater

Analysis of Postulated Accident Scenarios for the Transformational Challenge Reactor