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LWR Sustainability (LWRS) Program Status Uprate. Dr. Hongbin Zhang Idaho National Laboratory Hongbin.Zhang@inl.gov 208-526-9511 . International RELAP5 Users Group Meeting and Seminar Salt Lake City, July 25-28, 2011. LWRS Vision, Goals, and Scope. Vision
Dr. Hongbin Zhang
Idaho National Laboratory
International RELAP5 Users Group Meeting and Seminar
Salt Lake City, July 25-28, 2011
Analysis of cable degradation
Crack initiation in Ni-base alloys
Mechanisms of IASCC
Swelling of core internals
High fluence effects on RPV
Surrogate materials and attenuation
High fluence phase transformations
Advanced replacement alloys
Buried piping analysis
Proactive Materials Degradation Assessment Matrix
Combining Probabilistic and Mechanistic Modeling to provide Integrated Quantification of Aleatory and Epistemic Uncertainty
Area 1: Develop R7 to simulate plant dynamics and analyze safety margin
Area 2: Develop a risk-informed, simulation-driven methodology to drive R7 in analysis of plant safety margin
Area 3: Develop models of passive SSCs for application within R7, coupling phenomenology to SSC behavior
Go beyond the current technology manifested by legacy codes (RELAP5, SAPHIRE) developed at INL and used broadly by the industry and regulatory evaluation
Overcome limitations of 1970s’ “divide and conquer” paradigm
Push envelope of M&S in all physical processes involved in plant safety
Develop R7 code architecture and test version engine
Analyze a plant safety issue of importance for life extension
Demonstrate viability of using the R7 capability to construct the RISMC “safety case” on the selected life extension issue
Leverage on advances in applied math, computer and computational science
Zircaloy-4 tube for TiN coating
Samples under optical microscope before annealing: uncoated Zr-4 (left), 1mm TiN coated Zr-4 (right)
Samples under optical microscope after annealing: uncoated Zr-4 (left), 1mm TiN coated Zr-4 (right)
Surface morphology is changed for the bare substrate, while the sample coated with TiNshowed little or no change (no dilamination) in surface.
The coatings that survive corrosion testing will go into ATR for neutron irradiation testing
High resolution, 3D fuel performance calculation reveals the impact of a missing pellet surface on stress state, temperature profile, etc. (i.e. full nuclear fuel performance) as a function of fuel history.
Cross-Cutting with Advanced LWR Fuels Development
Goal: Facilitate power uprates for operating LWRs – identify, investigate obstacles and resolve issues that inhibit potential power uprates in aging fleet
J. Laine and M. Puustinen, Thermal stratification experiments with the condensation pool test rig, NKS-117, 2006.
* NRC draft guidance for use of containment accident pressure in determining the NPSH margin of ECCS and containment heat removal pumps.