Benchmark Physics Tests in the Metallic-Fueled Assembly ZPPR-15

Neutronics Modeling and Simulation of Sharp for Fast Reactor Analysis

“…The experiments analyzed include eight critical assemblies [51] of Los Alamos National Laboratory (LANL), ZPR-6 Assemblies 6A (ZPR-6/6A) and 7 (ZPR-6/7) [51,52], three loadings of ZPPR-15A [53], six phases of ZPPR-21 [51], and three BFS assemblies [52,54]. Using the ENDF/B-VII.0 data [55], isotopic multigroup cross sections were generated for each composition using MC 2 -3.…”

Argonne Reactor Code Software Verification and Validation Plan for the Versatile Test Reactor

“…As an alternative, we can rely upon previous experiments and operational reactor data to meet our validation needs. In this regard, we have a substantial database of experimental measurements on zero power critical mockups, ZPPR [18] along with historical data from the operating fast spectrum reactors EBR-II [19] and FFTF [20]. While none of these systems are perfectly identical to the proposed VTR, they provide sufficient basis to rigorously test the ARC software.…”

“…This relies on the assumption that the VTR core design is defined to a sufficient level of details allowing to identify representative systems. Based on the reference VTR core design [18], systems that could be used to perform the ARC software validation have been identified. Currently, only US-based systems are being considered to ensure we can more easily access the required data, and these systems are introduced in the following three sub-sections.…”

A Validation Study of Existing Neutronics Tools against ZPPR-21 and ZPPR-15 Critical Experiments

“…These experiments were previously analyzed in 1989 [3]. However, the analysis was mainly performed with three-dimensional nodal diffusion theory and 21-group cross sections, to be consistent with the core analysis methods at that time.…”

“…The ZPPR-15 experiments were conducted from April 1985 through July 1986 under the Integral Fast Reactor (IFR) Benchmark Physics Test Program [2,3]. The focus of the program was to provide experimental support for core designs using metallic alloy fuel.…”