Analysis of ZPPR-15 experimental data for VTR software validation
Journal Article
·
· Annals of Nuclear Energy
- Argonne National Lab. (ANL), Argonne, IL (United States)
As part of the Versatile Test Reactor (VTR) program, extensive validation work is being performed to demonstrate the fidelity of the Argonne Reactor Code (ARC) software package presently used for the core design studies. It is anticipated that this software will be also used for initial operations although additional software may be introduced at a later time to supplement or replace some components. The validation work was focused on accumulating reactor models that are consistent with the VTR and thus can be used to validate the accuracy of predictions made by the software used to design and operate the VTR. The U.S. does not have any active experimental facilities that can neutronically mockup the VTR core design. However, in the past, the U.S. had extensive experimental facilities for fast reactor neutronics. In that regard, the ZPPR-15 experiments carried out at ANL during the 1980s work best because the fuel form is closest to the VTR design, there is a considerable amount of processed data available for use, and existing staff are already familiar with the experimental machine and measurements. Because of previous collaborative work, many of the ZPPR-15 loadings of interest have already been processed into MCNP and preliminary ARC models, and a full uncertainty quantification has already been completed for many of the ZPPR-15 measurements. This manuscript covers the recent analysis work on the ZPPR-15 experiments and compares it with the experimental results. With respect to the ARC software components, this manuscript focuses on validation of the MC2, DIF3D and GAMSOR using the ZPPR-15 experimental data.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- Grant/Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1864290
- Alternate ID(s):
- OSTI ID: 1815058
OSTI ID: 23197105
- Journal Information:
- Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 159; ISSN 0306-4549
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Nuclear data sensitivity, uncertainty and target accuracy assessment for future nuclear systems
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journal | May 2006 |
Benchmark Physics Tests in the Metallic-Fueled Assembly ZPPR-15
|
journal | February 1989 |
| RCT - A Code to Reconstruct Pin Power and Burnup Characteristics from Nodal Calculations in Hexagonal Geometry | report | April 1993 |
| DIF3D-VARIANT 11.0: A Decade of Updates | report | April 2014 |
| SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis | report | August 1980 |
| User's guide for the REBUS-3 fuel cycle analysis capability | report | March 1983 |
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