The ORIGEN-S code in the SCALE 6.0 nuclear analysis code suite is a well-validated tool to calculate the time-dependent concentrations of nuclides due to isotopic depletion, decay, and transmutation for many systems in a wide range of time scales. Application areas include nuclear reactor and spent fuel storage analyses, burnup credit evaluations, decay heat calculations, and environmental assessments. Although simple to use within the SCALE 6.0 code system, especially with the ORIGEN-ARP graphical user interface, it is generally complex to use as a component within an externally developed code suite because of its tight coupling within the infrastructure of the larger SCALE 6.0 system. The ORIGEN2 code, which has been widely integrated within other simulation suites, is no longer maintained by Oak Ridge National Laboratory (ORNL), has obsolete data, and has a relatively small validation database. Therefore, a modular version of the SCALE/ORIGEN-S code was developed to simplify its integration with other software packages to allow multi-physics nuclear code systems to easily incorporate the well-validated isotopic depletion, decay, and transmutation capability to perform realistic nuclear reactor and fuel simulations. SCALE/ORIGEN-S was extensively restructured to develop a modular version that allows direct access to the matrix solvers embedded in the code. Problem initialization and the solver were segregated to provide a simple application program interface and fewer input/output operations for the multi-physics nuclear code systems. Furthermore, new interfaces were implemented to access and modify the ORIGEN-S input variables and nuclear cross-section data through external drivers. Three example drivers were implemented, in the C, C++, and Fortran 90 programming languages, to demonstrate the modular use of the new capability. This modular version of SCALE/ORIGEN-S has been embedded within several multi-physics software development projects at ORNL, including the AMP Nuclear Fuel Performance code and the NESTLE advanced nodal code.
[1]
K. Lassmann,et al.
Analysis of fuel centre temperatures with the TRANSURANUS code
,
2003
.
[2]
O. W. Hermann,et al.
ORIGEN-S : SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buidup and Decay, and Associated Radiation Source Terms
,
2000
.
[3]
G. Ivan Maldonado,et al.
Initial Validation of the AMP Nuclear Fuel Performance Code
,
2010
.
[4]
G. I. Maldonado,et al.
Integration of the NESTLE Core Simulator with SCALE
,
2009
.
[5]
Paul J. Turinsky,et al.
NESTLE. Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method
,
1994
.
[6]
Mark D. DeHart,et al.
Lattice Physics Capabilities of the SCALE Code System Using TRITON
,
2006
.