Data Compilation for AGR-2 UCO Variant Compact Lot LEU06-OP1-Z
This document is a compilation of characterization data for the candidate AGR-2 UCO Baseline fuel compact lot LEU07-OPI-Z. The compacts were produced by ORNL for the Advanced Gas Reactor Fuel Development and Qualification (AGR) program for the second AGR irradiation test (AGR-2). This compact lot was fabricated using particle composite LEU07. LEU07 came from Babcock and Wilcox (B&W) coated particle lot G73J-14-92072A, which was an upgraded batch of TRISO-coated 425 μm diameter, 14% low enrichment uranium oxide/uranium carbide kernels (LEUCO). The AGR-2 TRISO-coated particles consist of a spherical kernel coated with an ~50% dense carbon buffer layer (100 μm nominal thickness), followed by a SiC layer (35 μm nominal thickness), followed by another dense outer pyrocarbon layer (40 μm nominal thickness). The kernels were also manufactured by B&W and identified as kernel lot G73I-14-69307. Two data packages were submitted by B&W containing the acceptance testing results for the kernels and coated particles, these are identified by their lot numbers. A discussion on the coating of the B&W TRISO particles can also be found in INL report INL/EXT-09-16545. A data compilation of ORNL analysis of G73J-14-93072A can be found in ORNL/TM-2008/133. The AGR-2 Fuel Specification (INL SPC-923) provides the requirements necessary for acceptance of the fuel manufactured for the AGR-2 irradiation test. Section 3.3 of SPC-923 provides the property requirements for the heat treated compacts. The Statistical Sampling Plan for AGR-2 Fuel Materials (INL PLN-2691) provides additional guidance regarding statistical methods for product acceptance and recommended sample sizes. The procedures for characterizing and qualifying the compacts are outlined in ORNL product inspection plan AGR-CHAR-PIP-11 to obtain data needed for calculation of compacting charge weight and matrix density. Riffling of compact charges is also covered by this procedure. Prior to overcoating, the TRISO particles are characterized per ORNL product inspection plan AGR-CHAR-PIP-10 to determine uranium content, obtain data need for overcoating and compact fabrication, and obtain further data needed for calculation of matrix density. Riffling of overcoater charges is also covered by this procedure. This document contains all the inspection report forms and data report forms generated by these inspection plans. In addition to the characterization data, this report also contains other records relevant to the fuel product acceptance. A history of the material flow and sample naming is included. The overcoating and compacting process is summarized. A record of the materials use to make the matrix is also included. A Certificate of Conformance and any applicable Nonconformance Reports are attached as Appendices.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1632081
- Report Number(s):
- ORNL/TM-2009/304; TRN: US2200845
- Country of Publication:
- United States
- Language:
- English
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Data Compilation for AGR-2 UCO Baseline Compact Lot LEU07-OP1-Z
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