Qualification of Metallic Fuel Data for Advanced SFR Applications

Yacout, Abdellatif M.; Mo, Kun; Oaks, Aaron; Billone, Michael; Miao, Yinbin; Alicz, Jeffrey

doi:10.1080/00295450.2022.2105779

Qualification of Metallic Fuel Data for Advanced SFR Applications

Journal Article · Tue Sep 13 00:00:00 EDT 2022 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2022.2105779· OSTI ID:1886981

Yacout, Abdellatif M. ^[1]; Mo, Kun ^[1]; Oaks, Aaron ^[1]; Billone, Michael ^[1]; Miao, Yinbin ^[1]; Alicz, Jeffrey ^[1]

Argonne National Laboratory (ANL), Argonne, IL (United States)

Metallic fuel is proposed for use in various advanced sodium-cooled fast reactor (SFR) designs, including small modular reactors and microreactors. To support advanced SFR research and development, a metallic fuel database has been developed at Argonne National Laboratory. The database was built on extensive metallic fuel data collected during the Integral Fast Reactor Program, mainly from irradiation experiments in the Experimental Breeder Reactor-II (EBR-II). In order to manage the large amount of data and associated documents and to qualify the data, a Quality Assurance Program Plan (QAPP) was established for the legacy metallic fuel data following the American Society of Mechanical Engineers (ASME) Nuclear Quality Assurance (NQA-1) 2008/2009 Addenda Standard. Metallic fuel data qualification is being performed following the QAPP. The plan has been approved by the U.S. Nuclear Regulatory Commission and can be referenced in licensing applications for nuclear power plants. The process for qualifying metallic fuel data is presented. The structure for implementing the QAPP and the qualification methods are introduced. The principle for prioritizing the metallic fuel data for quality assurance is summarized. An overview of the metallic fuel data available and considered for qualification is also provided.

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Research Organization:: Argonne National Laboratory (ANL), Argonne, IL (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1886981

Alternate ID(s):: OSTI ID: 1994553

Journal Information:: Nuclear Technology, Vol. 209, Issue sup1; ISSN 0029-5450

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

References (21)

Legacy Metal Fuel Data Exploration for Commercial Scale-Up Yacout, Abdellatif M. https://doi.org/10.2172/1496023	report	February 2019
The intergral fast reactor-an overview Till, C. E.; Chang, Y. I.; Hannum, W. H. Progress in Nuclear Energy, Vol. 31, Issue 1-2 https://doi.org/10.1016/0149-1970(96)00001-7	journal	January 1997
VTR Startup Fuel Paper for NFSM Crawford, Douglas C.; Hayes, Steven L.; Powers, Jeffery J. https://doi.org/10.2172/1478518	report	February 2018
SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis Basehore, K. L.; Todreas, N. E. https://doi.org/10.2172/5107861	report	August 1980
Cladding Profilometry Analysis of Experimental Breeder Reactor-II Metallic Fuel Pins with HT9, D9, and SS316 Cladding Paaren, Kyle M.; Lybeck, Nancy; Mo, Kun Energies, Vol. 14, Issue 2 https://doi.org/10.3390/en14020515	journal	January 2021
Experience with advanced driver fuels in EBR-II Lahm, C. E.; Koenig, J. F.; Pahl, R. G. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90207-F	journal	September 1993
DIF3D: a code to solve one-, two-, and three-dimensional finite-difference diffusion theory problems. [LMFBR] Derstine, K. https://doi.org/10.2172/7157044	report	April 1984
Performance of U-Pu-Zr fuel cast into zirconium molds Crawford, D. C.; Lahm, C. E.; Tsai, H. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90212-H	journal	September 1993
Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data Yacout, A. M.; Billone, M. C. https://doi.org/10.2172/1418818	report	September 2016
FY20 Progress Report on FIPD Development and User Support Oaks, A.; Mo, K.; Miao, Y. https://doi.org/10.2172/1821697	report	September 2020
FIPD: The SFR metallic fuels irradiation & physics database Yacout, Abdellatif M.; Mo, Kun; Oaks, Aaron Nuclear Engineering and Design, Vol. 380 https://doi.org/10.1016/j.nucengdes.2021.111225	journal	August 2021
Quality Assurance Program Plan for SFR Metallic Fuel Data Qualification Benoit, Timothy; Mo, Kun; Yacout, Abdellatif https://doi.org/10.2172/1524412	report	May 2019
EBRFLOW–A Computer Program for Predicting the Coolant Flow Distribution in the Experimental Breeder Reactor-II Gopalakrishnan, A.; Gillette, J. L. Nuclear Technology, Vol. 17, Issue 3 https://doi.org/10.13182/NT73-A31264	journal	March 1973
Experimental studies of U-Pu-Zr fast reactor fuel pins in the experimental breeder reactor-ll Pahl, R. G.; Porter, D. L.; Lahm, C. E. Metallurgical Transactions A, Vol. 21, Issue 7 https://doi.org/10.1007/BF02647233	journal	July 1990
Software Quality Assurance for EBR-II Fuels Irradiation and Physics Database (FIPD) Smith, Micheal; Ibarra, Lander; Oaks, Aaron https://doi.org/10.2172/1823468	report	September 2021
Summary description of the Fast Flux Test Facility Cabell, C. P. https://doi.org/10.2172/6032523	report	December 1980
RCT - A Code to Reconstruct Pin Power and Burnup Characteristics from Nodal Calculations in Hexagonal Geometry Yang, W. S. https://doi.org/10.2172/10198080	report	April 1993
Initial demonstration of automated fuel performance modeling with 1977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases Paaren, Kyle M.; Gale, Micah; Kerr, Matthew J. Nuclear Engineering and Design, Vol. 382 https://doi.org/10.1016/j.nucengdes.2021.111393	journal	October 2021
MC/sup 2/-2: a code to calculate fast neutron spectra and multigroup cross sections. [LMFBR] Henryson, H. Ii; Toppel, B. J.; Stenberg, C. G. https://doi.org/10.2172/7143331	report	January 1976
The Integral Fast Reactor Chang, Yoon I. Nuclear Technology, Vol. 88, Issue 2 https://doi.org/10.13182/NT88-129	journal	December 1989
User's guide for the REBUS-3 fuel cycle analysis capability Toppel, B. J. https://doi.org/10.2172/6068571	report	March 1983

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