Code Testing

Software quality is tightly controlled using issue tracking, automatic testing or merge requests, and collaborative code review. 

Through MOOSE, Rattlesnake is supported by more than 2000 tests.  All new code must be supported by testing.


The verification of Rattlesnake will be documented in the future. However, this verification relies largely on the tests described above, and is built on the MOOSE verification plan. Rattlesnake has been or is currently being verified against a number of existing benchmarks for both steady state and radiation transport calculations.  These include the following benchmarks: C5G7 [1], LRA BWR kinetics [2], Kobayashi [3], IAEA 3-D PWR [4], KAIST-3A reactor quarter core [5], C5G7-TD Time Dependent Benchmark [6], etc. In addition, as the transport solver within MAMMOTH, Rattlesnake is verified as part of each of the multi-physics solutions used for MAMMOTH validation. Some of the validation problems are BEAVRS [7], OECD 3-D MHTGR-350 Core [8], TREAT Minimum Core [9], etc.


1. OECD/NEA, Benchmark on deterministic transport calculations without spatial homogenization A 2-D/3-D MOX fuel assembly benchmark,  ISBN 92-64- 02139-6

2. Argonne Code Center. Benchmark Problem Book, ANL- 7416, Suppl. 2. Technical report, Argonne National Laboratory (1977).

3. Keisuke Kobayashi, Naoki Sugimura, Yasunobu Nagaya, 3-D RADIATION TRANSPORT BENCHMARK PROBLEMS AND RESULTS FOR SIMPLE GEOMETRIES WITH VOID REGIONS, Nuclear Energy Agency of the OECD (NEA): Organisation for Economic Co-Operation and Development - Nuclear Energy Agency (2000)

4. Benchmark Problem Book, ANL-7416, Suppl. 2, Argonne National Laboratory (1977)

5. Nam Zin, Cho, Benchmark Problems in Reactor and Particle Transport Physics, Available at, (2000)

6. OECD/NEA Deterministic Time-Dependent Neutron Transport Benchmark without Spatial Homogenization (C5G7-TD), (2017)

7. N. Horelik, B. Herman, B. Forget, and K. Smith. “Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS),” v1.0.1. Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuc. Sci. & Eng., Sun Valley, Idaho (2013).

8. J. Ortensi, et al., “Prismatic Core Coupled Transient Benchmark”, INL/CON-11- 20811.

9. Javier Ortensi, Anthony Alberti, Yaqi Wang, Mark D. DeHart, Frederick N. Gleicher, Sebastian Schunert, Todd S. Palrmer,"Methodologies and Requirements for the Generation of Physics Data Inputs to MAMMOTH Transient Simulations in Support of the Transient Reactor Test Facility; INL/LTD-15- 36265, September 2015.


Rattlesnake is a multigroup transport solver with geometry mesh and the cross sections being the inputs, thus validation of Rattlesnake does not apply.