Benchmark Matrix for Verification and Validation of DeCART2D Code
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Assembly problems w/o burnable absorber (BA) - Assembly problems w/ BA - Rod worth problems - Burnup problems All the problem specifications in the benchmark matrix are based on the 17x17 SMART fuel assembly (FA) design and provided in various operating conditions. The 47/18 neutron/gamma energy group XS library based on the ENDF/B-VII.1 is used with 0.02 cm ray spacing, 8 azimuthal angles in 90° domain and 2 polar angles for ray discretization. The results of calculations are compared with the Monte Carlo codes such as McCARD and MCNP. In the subsequent section, the detailed characteristics of each body of a benchmark suite will be provided. A benchmark suite for the DeCART2D code is developed to verify and validate its calculation performance. The maximum eigenvalue error between DeCART2D and MCNP is appeared to be -426 pcm for the BOL problems, while it is -415pcm when compared to McCARD. The largest errors in pin power are - 0.72% when the reference is MCNP, while it is -0.80% for McCARD.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Spring Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [4 p.]
Conference
- Title
- 2018 Spring Meeting of the KNS
- Dates
- 16-18 May 2018
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50059235
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCHMARKS; BOLTZMANN EQUATION; D CODES; DESIGN; EIGENVALUES; KAERI; MONTE CARLO METHOD; PWR TYPE REACTORS; SPECIFICATIONS; VALIDATION; VERIFICATION
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; INTEGRO-DIFFERENTIAL EQUATIONS; KINETIC EQUATIONS; KOREAN ORGANIZATIONS; NATIONAL ORGANIZATIONS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 7 figs, 6 tabs