- Replace the process of running ~800+ code runs with five lines of input to SNF, which eliminates large consulting fees and long project times.
- Best-Estimate Source Term reduces typical uncertainties.
- State-of-the-Art, most recent Nuclear Data (ENDF/ B-VIII.0 available) removes the need for hand- calculated corrections from older libraries.
SNF calculates isotopic concentrations, radiation source terms, and decay heat of spent light water reactor (LWR) fuel. By using the detailed, 3D power history from SIMULATE and isotopic inventories from CASMO, SNF provides the most accurate spent fuel analysis available.
Created at the Request of Customers:
- Explicitly calculate decay heat.
- Explicitly calculate decay chains for safeguards isotopic inventory reporting.
- Rapidly determine source term in pools, casks, and final repository.
Remove Complication. Remove Cost.
Extensive Validation
- SNF has been validated against both international measurements and existing reference codes, such as ORIGEN.
- Source term validation has been performed against measured neutron emission rates of isotopes such as 242Cm, 244Cm, and 246Cm.
- SNF also excelled in comparisons with fuel assembly decay heat measurements of a large number of BWR and PWR spent fuel assemblies at the CLAB storage facility in Sweden.
Consistent Methods, In-Core and Out
SNF leverages the multi-dimensional methods of CASMO and SIMULATE to provide a robust evaluation of isotopic concentrations, radiation source terms, neutron and photon spectra, and decay heat of spent nuclear fuel.
Utilizing the detailed power histories, and the explicit nodal representation of the fuel assemblies, SNF ensures unparalleled fidelity. Any configuration of light water reactor fuel that can be modeled in CASMO may be analyzed with SNF. Multiple international standards are integrated into SNF for complementary information in comparison to explicit SNF calculations.
Applications
SNF provides easy-to-use reports of radioactivity, photon and neutron spectra, and decay heat for use in cask loading design and optimization. Additionally, SNF can be used by reactor engineers to assess the decay heat of fuel in the reactor during shutdown or in the spent fuel pool. SNF has been coupled to GARDEL, Studsvik’s on-line core monitoring software, for real-time decay heat calculations for the operating core.
Ease of use
SNF requires little effort from the user to produce detailed spent fuel assessments. All that is required is an isotopic library from CASMO and, optionally, power history results from SIMULATE. SNF complements Studsvik’s in-core fuel management suite, providing the ability to support the entire nuclear fuel lifecycle.
Enhanced Modeling
SNF includes enhanced mixed-oxide (MOX) modeling, additional actinide data for decay times up to 1 million years, and the most current neutron yield data. These improvements, coupled with Studsvik’s industry-leading fuel management methods, make SNF the most reliable spent fuel analysis tool available.
Fuel Cask Utilization
SNF has been shown to increase cask utilization (i.e., fewer unloaded locations) by reducing conservatism in decay heat predictions versus conventional cask loading tools. The robust models and detailed fuel history data used by SNF can help prevent partially loaded storage casks, saving money in engineering time and costly cask loads.