Fluence
Component aging and stress-induced corrosion cracking are leading to more frequent and more thorough component inspections and repairs. Fluence is the primary contributor to material degradation and can be the deciding factor when it comes to repair options. An accurate assessment of fluence should be a primary goal of your component maintenance programs. TransWare is ready to help you with support for license renewal applications, flaw evaluations, equipment qualifications, and fluence maintenance programs for your pressure vessel and reactor components. Our true 3-D methodology allows for the accurate modeling of all internal components, such as:
| BWRs | PWRs |
| Core Shroud and Repair Assemblies | Core Barrel |
| Core Support Plate and Rim Bolts | Upper and Lower Core Plates |
| Top Guide | Neutron Pads |
| Core Spray Spargers | Baffle Plates |
| Jet Pump Assemblies and Hardware | Vessel Support Structures |
| Vessel Insulation | Vessel Insulation |
| RPV and Nozzle Penetrations |
RPV and Nozzle Penetrations |
| Biological Shield | Biological Shield |
TransWare is the principal developer of the RAMA Fluence Methodology, a three-dimensional, deterministic particle transport code which is approved for use in RPV and internal component fluence calculations by the U. S. Nuclear Regulatory Commission. Our plant-specific approach utilizes as-built drawings to build plant-specific models. This approach has allowed us to achieve approval from the NRC to perform fluence calculations with a zero bias. In addition, we're continuosly developing and innovating this crucial area of plant support. In 2010 we completed the development of a production-ready thermal fluence cross-section library. Thermal fluence is of great importance in determining the weldability of vessels and their internal components (for more information, see our brochure).
There are many benefits to performing your fluence evaluations with TransWare and the RAMA Fluence Methodology:
- A code approved by the NRC for fluence evaluations
- More than 1000 measurement comparisons to plant and simulator dosimetry with an overall C/M of 1.02 +/- 0.10
- An experienced set of engineers familiar with all breeds of BWR and PWR plant internals
- Fast and thermal neutron fluence solutions
- Reliable fluence predictions that meet Reg. Guide requirements for uncertainty
- Precise 3-D treatment of all internal components, no 2-D approximations