FIPD: The SFR metallic fuels irradiation &amp; physics database

Yacout, Abdellatif M.; Mo, Kun; Oaks, Aaron; Miao, Yinbin; Sofu, Tanju; Mohamed, Walid

doi:10.1016/j.nucengdes.2021.111225

FIPD: The SFR metallic fuels irradiation & physics database

Journal Article · Thu May 13 00:00:00 EDT 2021 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2021.111225· OSTI ID:1837086

^[1]; ^[1]; ^[1]; ^[1]; Sofu, Tanju ^[1]; ^[1]

Argonne National Lab. (ANL), Argonne, IL (United States)

The DOE Advanced Reactor Technology (ART) program has supported efforts to recover and preserve metallic fuel data generated throughout the US sodium-cooled fast reactor (SFR) program. Those efforts have been focused on establishing databases of the experimental data that were mainly generated during the Integral Fast Reactor (IFR) program including data generated at Experimental Breeder Reactor-II (EBR-II), Fast Flux Test Facility (FFTF), and Transient Reactor Test Facility (TREAT) reactors, as well as out of pile data. The data is essential for future licensing activities of metallic fuel based advanced fast reactors. This paper describes the development of the SFR Metallic Fuels Irradiation & Physics Database (FIPD) and covers the scientific knowledge available in the database. Furthermore, the architecture of the FIPD is described by showing the available reactor operation data, fabrication, and post-irradiation examination (PIE) data, and other documents. The applications of the fuel database are also discussed.

View Accepted Manuscript (DOE)

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:: 1837086

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 380; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (32)

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
Fuel constituent redistribution during the early stages of U-Pu-Zr irradiation Porter, D. L.; Lahm, C. E.; Pahl, R. G. Metallurgical Transactions A, Vol. 21, Issue 7 https://doi.org/10.1007/BF02647234	journal	July 1990
Swelling behavior of U-Pu-Zr fuel Hofman, Gerard L.; Pahl, R. G.; Lahm, C. E. Metallurgical Transactions A, Vol. 21, Issue 2 https://doi.org/10.1007/BF02671924	journal	February 1990
Irradiation behavior of metallic fast reactor fuels Pahl, R. G.; Porter, D. L.; Crawford, D. C. Journal of Nuclear Materials, Vol. 188 https://doi.org/10.1016/0022-3115(92)90447-S	journal	June 1992
Performance of HT9 clad metallic fuel at high temperature Pahl, R. G.; Lahm, C. E.; Hayes, S. L. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90210-P	journal	September 1993
Kinetics of fission-gas-bubble-nucleated void swelling of the alpha-uranium phase of irradiated U-Zr and U-Pu-Zr fuel Rest, J. Journal of Nuclear Materials, Vol. 207 https://doi.org/10.1016/0022-3115(93)90261-V	journal	December 1993
Temperature gradient driven constituent redistribution in UZr alloys Hofman, G. L.; Hayes, S. L.; Petri, M. C. Journal of Nuclear Materials, Vol. 227, Issue 3 https://doi.org/10.1016/0022-3115(95)00129-8	journal	January 1996
Demonstration of EBR-II power maneuvers without control rod movement Chang, L. K.; Mohr, D.; Planchon, H. P. Nuclear Engineering and Design, Vol. 113, Issue 1 https://doi.org/10.1016/0029-5493(89)90304-X	journal	April 1989
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
Statistical failure analysis of metallic U-10zr/HT9 fast reactor fuel pin by considering the weibull distribution and cumulative damage fraction Nam, Cheol; Hwang, Woan; Sohn, Dong-Seong Annals of Nuclear Energy, Vol. 25, Issue 17 https://doi.org/10.1016/S0306-4549(98)00043-7	journal	November 1998
Development and validation of thermo-mechanical analysis code of metallic fuel under steady-state conditions in LMFR Sun, Hongping; Zhang, Yapei; Tian, Wenxi Annals of Nuclear Energy, Vol. 138 https://doi.org/10.1016/j.anucene.2019.107221	journal	April 2020
Constituent redistribution in U–Pu–Zr fuel during irradiation Kim, Yeon Soo; Hofman, G. L.; Hayes, S. L. Journal of Nuclear Materials, Vol. 327, Issue 1 https://doi.org/10.1016/j.jnucmat.2004.01.012	journal	April 2004
Modeling of constituent redistribution in U–Pu–Zr metallic fuel Kim, Yeon Soo; Hayes, S. L.; Hofman, G. L. Journal of Nuclear Materials, Vol. 359, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2006.07.013	journal	December 2006
Fuels for sodium-cooled fast reactors: US perspective Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.010	journal	September 2007
A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design Burkes, Douglas E.; Fielding, Randall S.; Porter, Douglas L. Journal of Nuclear Materials, Vol. 389, Issue 3 https://doi.org/10.1016/j.jnucmat.2009.02.035	journal	June 2009
Migration of minor actinides and lanthanides in fast reactor metallic fuel Kim, Yeon Soo; Hofman, G. L.; Yacout, A. M. Journal of Nuclear Materials, Vol. 392, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.03.043	journal	July 2009
Multidimensional multiphysics simulation of nuclear fuel behavior Williamson, R. L.; Hales, J. D.; Novascone, S. R. Journal of Nuclear Materials, Vol. 423, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.01.012	journal	April 2012
A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents Sofu, Tanju Nuclear Engineering and Technology, Vol. 47, Issue 3 https://doi.org/10.1016/j.net.2015.03.004	journal	April 2015
Modeling constituent redistribution in U–Pu–Zr metallic fuel using the advanced fuel performance code BISON Galloway, J.; Unal, C.; Carlson, N. Nuclear Engineering and Design, Vol. 286 https://doi.org/10.1016/j.nucengdes.2015.01.014	journal	May 2015
Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review Matthews, Christopher; Unal, Cetin; Galloway, Jack Nuclear Technology, Vol. 198, Issue 3 https://doi.org/10.1080/00295450.2017.1323535	journal	June 2017
Design of the 4S Reactor Tsuboi, Yasushi; Arie, Kazuo; Ueda, Nobuyuki Nuclear Technology, Vol. 178, Issue 2 https://doi.org/10.13182/NT10-74	journal	May 2012
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
Irradiation Behavior of Experimental Mark-II Experimental Breeder Reactor II Driver Fuel Hofman, G. L. Nuclear Technology, Vol. 47, Issue 1 https://doi.org/10.13182/NT80-A32408	journal	January 1980
Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors Walters, Leon C.; Seidel, B. R.; Kittel, J. Howard Nuclear Technology, Vol. 65, Issue 2 https://doi.org/10.13182/NT84-A33408	journal	May 1984
The Integral Fast Reactor Chang, Yoon I. Nuclear Technology, Vol. 88, Issue 2 https://doi.org/10.13182/NT88-129	journal	December 1989
In-Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel Bauer, Theodore H.; Holland, John W. Nuclear Technology, Vol. 110, Issue 3 https://doi.org/10.13182/NT95-A35110	journal	June 1995
Degradation Analysis Estimates of the Time-to-Failure Distribution of Irradiated Fuel Elements Yacout, Abdellatif M.; Salvatores, Stefano; Orechwa, Yuri Nuclear Technology, Vol. 113, Issue 2 https://doi.org/10.13182/NT96-A35187	journal	February 1996
Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data Yacout, A. M.; Billone, M. C. https://doi.org/10.2172/1418818	report	September 2016
Legacy Metal Fuel Data Exploration for Commercial Scale-Up Yacout, Abdellatif M. https://doi.org/10.2172/1496023	report	February 2019
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
Summary description of the Fast Flux Test Facility Cabell, C. P. https://doi.org/10.2172/6032523	report	December 1980
User's guide for the REBUS-3 fuel cycle analysis capability Toppel, B. J. https://doi.org/10.2172/6068571	report	March 1983

Similar Records

FIPD: EBR-II Fuels Irradiation & Physics Database – FY19 Updates

Technical Report · Mon Sep 23 00:00:00 EDT 2019 · OSTI ID:1821696

FIPD: EBR-II Fuels Irradiation & Physics Database

Technical Report · Mon Sep 18 00:00:00 EDT 2017 · OSTI ID:1480520

Summary Report for Out-of-Pile Transient Testing Database Development

Technical Report · Mon Sep 30 00:00:00 EDT 2019 · OSTI ID:1811301

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BISON
EBR-II
fast reactors
fuel performance modeling
metallic fuel

FIPD: The SFR metallic fuels irradiation & physics database

Citation Formats

References (32)

Similar Records

Related Subjects