Published 2005 | Version v1
Computer medium

New CRISTAL standards applicability for the French FRAMATOME ANP uranium fuel fabrication plant

  • 1. Framatome ANP Fuel Sector, An AREVA and Siemens Company, FRAMATOME ANP, Lyon (France)
  • 2. Framatome ANP Fuel Sector, Fuel Fabrication Plant FBFC, FRAMATOME ANP, Lyon (FR)

Description

Criticality safety evaluations implement requirements to proof of sufficient sub critical margins outside of the reactor environment for example in fuel fabrication plants. Basic criticality data (i.e., criticality standards) are used in the determination of sub critical margins for all processes involving plutonium or enriched uranium. There are several criticality worldwide standards, e.g., ARH-600, which the US nuclear industry relies on. The French Nuclear Safety Authority (DGSNR and its advising body IRSN) has requested Framatome ANP to review the criticality standards used for the evaluation of its Low Enriched Uranium fuel fabrication plants with CRISTAL V0, the recently updated French criticality evaluation package. Criticality safety is a concern for every phase of the fabrication process including UF6 cylinder storage, UF6-UO2 conversion, powder storage, pelletizing, rod loading, assembly fabrication, and assembly transportation. Until 2003, the accepted criticality standards were based on the French CEA work performed in the late seventies with the APOLLO1 cell/assembly computer code. APOLLO1 is a spectral code, used for evaluating the basic characteristics of fuel assemblies for reactor physics applications, which has been enhanced to perform criticality safety calculations. Throughout the years, CRISTAL, starting with APOLLO1 and MORET 3 (a 3D Monte Carlo code), has been improved to account for the growth of its qualification database and for increasing user requirements. Today, CRISTAL V0 is an up-to-date computational tool incorporating a modern basic microscopic cross section set based on JFE2.2 and the comprehensive APOLLO2 and MORET 4 codes. APOLLO2 is well suited for criticality standards calculations as it includes a sophisticated self shielding approach, a Pij flux determination, and a 1D transport (Sn) process. CRISTAL V0 is the result of more than five years of development work focusing on theoretical approaches and the implementation of user-friendly graphical interfaces. Due to its comprehensive physical simulation and thanks to its broad qualification database with more than a thousand benchmark/calculation comparisons, CRISTAL V0 provides outstanding and reliable accuracy for criticality evaluations for configurations covering the entire fuel cycle (i.e. from enrichment, pellet/assembly fabrication, transportation, to fuel reprocessing). After a brief description of the calculation scheme and the physics algorithms used in this code package, results for the various fissile media encountered in a UO2 fuel fabrication plant will be detailed and discussed. (author)

Part of:
Proceedings of the 2005 water reactor fuel performance meeting

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of the 2005 water reactor fuel performance meeting
Imprint Pagination
[1236 p.]
Journal Page Range
[4 p.]

Conference

Title
2005 water reactor fuel performance meeting
Dates
2-6 Oct 2005
Place
Kyoto (Japan)

Optional Information

Notes
This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH and UNIX; Acrobat Reader is included; Data in PDF format, Folder Name papers, Paper ID 1135.pdf; 5 refs., 1 fig., 4 tabs.