Benchmark on deterministic transport calculations without spatial homogenization. MOX fuel assembly 3-D extension case
Description
Within the framework of the OECD/NEA Expert Group on 3-D Radiation Transport Benchmarks, an international benchmark exercise for testing the ability of modern deterministic transport methods and codes to treat reactor problems without spatial homogenization was proposed in March 2001. That benchmark was completed in 2003 and the OECD report is available. As a follow-up to that benchmark, an extension of the 3-D calculations was proposed in May 2003 to provide a more challenging test of present day three-dimensional methods ability to handle spatial homogeneities. The reactor core size was decreased to allow the calculations to be carried out within the limitations of present-day computers. Control rods were introduced, adding to the heterogeneity of the problems. Fourteen solutions were submitted for the new benchmark by twelve participants. All of the participant solutions were compared to a reference multigroup Monte Carlo solution. The analysis of results shows modern deterministic transport codes and methods can calculate the flux distribution reasonably well without relying upon spatial homogenization techniques, provided the domain size is small enough that the problem can be performed on available computing equipment. (author)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Paris (France)
- ISBN
- 92-64-01069-6
- Imprint Pagination
- 155 p.
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 37021768
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BENCHMARKS; COMPARATIVE EVALUATIONS; COMPUTER CODES; CONFIGURATION; DETERMINISTIC ESTIMATION; FUEL ASSEMBLIES; MIXED OXIDE FUELS; MONTE CARLO METHOD; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CALCULATION METHODS; ENERGY SOURCES; EVALUATION; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS