Experimental studies on metallic fuel relocation in a pin bundle core structure of a sodium-cooled fast reactor

Kim, Taeil; Harbaruk, Dzmitry; Lisowski, Darius; Bremer, Nathan; Farmer, Mitchell; Grandy, Christopher; Chang, Yoon Il

doi:10.1016/j.nucengdes.2020.110719

Experimental studies on metallic fuel relocation in a pin bundle core structure of a sodium-cooled fast reactor

Journal Article · Sat Jun 06 00:00:00 EDT 2020 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2020.110719· OSTI ID:1659758

^[1]; Harbaruk, Dzmitry ^[1]; Lisowski, Darius ^[1]; Bremer, Nathan ^[1]; Farmer, Mitchell ^[1]; Grandy, Christopher ^[1]; Chang, Yoon Il ^[1]

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

Understanding the relocation behavior of metallic fuel in severe accident scenarios is one of the most important factors in the safety assessment of sodium-cooled fast reactors (SFRs). In the present study, the relocation behavior of uranium metallic fuel was investigated by conducting metallic fuel relocation experiments using 19-pin bundle test sections in the Argonne's Metallic Uranium Safety Experiment (MUSE) facility. Post-test radiographic images were taken to characterize the uranium fuel relocation within the pin bundle test section. In addition, the pressure drop in the test sections was measured after the relocation experiments to evaluate the blockage of the sodium coolant channel. The pressure drop in the pin bundle test sections was also analytically calculated by varying the porosity and the pore size of the relocated fuel. The porosity and pore size of the relocated fuel in the pin bundle test sections were estimated by comparing those calculated pressure drop values with the measured pressure drop values from the pressure drop tests. In this work, the experimental results showed that the more formation of the eutectics could lead to more fuel dispersion and less blockage due to the lower freezing point of the eutectics.

View Accepted Manuscript (DOE)

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

Sponsoring Organization:: Korea Atomic Energy Research Institute (KAERI); USDOE

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1659758

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 365; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (14)

The interaction of iron with molten uranium Walter, C. M.; Kelman, L. R. Journal of Nuclear Materials, Vol. 20, Issue 3 https://doi.org/10.1016/0022-3115(66)90044-4	journal	September 1966
The experimental breeder reactor II inherent shutdown and heat removal tests — results and analysis Planchon, H. P.; Singer, R. M.; Mohr, D. Nuclear Engineering and Design, Vol. 91, Issue 3 https://doi.org/10.1016/0029-5493(86)90082-8	journal	February 1986
Experimental studies on eutectic formation between metallic fuel and HT-9M cladding in a single-pin core structure of a sodium-cooled fast reactor Kim, Taeil; Fortner, Jeffrey; Harbaruk, Dzmitry Journal of Nuclear Materials, Vol. 505 https://doi.org/10.1016/j.jnucmat.2018.04.003	journal	July 2018
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor Lee, Kwi Lim; Ha, Kwi-Seok; Jeong, Jae-Ho Nuclear Engineering and Technology, Vol. 48, Issue 5 https://doi.org/10.1016/j.net.2016.08.002	journal	October 2016
Transformation and fragmentation behavior of molten metal drop in sodium pool Nishimura, Satoshi; Zhang, Zhi-Gang; Sugiyama, Ken-Ichiro Nuclear Engineering and Design, Vol. 237, Issue 23 https://doi.org/10.1016/j.nucengdes.2007.03.021	journal	December 2007
Experimental studies on metallic fuel relocation in a single-pin core structure of a sodium-cooled fast reactor Kim, Taeil; Harbaruk, Dzmitry; Gerardi, Craig Nuclear Engineering and Design, Vol. 322 https://doi.org/10.1016/j.nucengdes.2017.06.049	journal	October 2017
Experimental study on fuel-discharge behaviour through in-core coolant channels Kamiyama, Kenji; Saito, Masaki; Matsuba, Ken-ichi Journal of Nuclear Science and Technology, Vol. 50, Issue 6 https://doi.org/10.1080/00223131.2013.785272	journal	June 2013
Visual study of ex-pin phenomena for SFR with metal fuel under initial phase of severe accidents by using simulants Heo, Hyo; Park, Seong Dae; Jerng, Dong Wook Journal of Nuclear Science and Technology, Vol. 53, Issue 9 https://doi.org/10.1080/00223131.2015.1120246	journal	January 2016
Thermal Fragmentation of a Molten Metal Jet Dropped into a Sodium Pool at Interface Temperatures below Its Freezing Point Nishimura, Satoshi; Kinoshita, Izumi; Sugiyama, Ken-ichiro Journal of Nuclear Science and Technology, Vol. 39, Issue 7 https://doi.org/10.1080/18811248.2002.9715257	journal	July 2002
Fragmentation of a Single Molten Metal Droplet Penetrating Sodium Pool I Copper Droplet and the Relationship with Copper Jet Zhang, Zhi-gang; Sugiyama, Ken-ichiro; Itagaki, Wataru Journal of Nuclear Science and Technology, Vol. 46, Issue 5 https://doi.org/10.1080/18811248.2007.9711552	journal	May 2009
Fragmentation of a Single Molten Metal Droplet Penetrating Sodium Pool II Stainless Steel and the Relationship with Copper Droplet Zhang, Zhi-gang; Sugiyama, Ken-ichiro Journal of Nuclear Science and Technology, Vol. 47, Issue 2 https://doi.org/10.1080/18811248.2010.9711942	journal	February 2010
Thermal Interaction between Molten Metal Jet and Sodium Pool: Effect of Principal Factors Governing Fragmentation of the Jet Nishimura, Satoshi; Kinoshita, Izumi; Sugiyama, Ken-Ichiro Nuclear Technology, Vol. 149, Issue 2 https://doi.org/10.13182/NT05-A3589	journal	February 2005
Behavior of Modern Metallic Fuel in TREAT Transient Overpower Tests Bauer, Theodore H.; Wright, Arthur E.; Robinson, William R. Nuclear Technology, Vol. 92, Issue 3 https://doi.org/10.13182/NT92-325	journal	December 1990
Technical Rationale for Metal fuel in fast Reactors Chang, Yoon-Il Nuclear Engineering and Technology, Vol. 39, Issue 3 https://doi.org/10.5516/NET.2007.39.3.161	journal	June 2007

Similar Records

Experimental studies on metallic fuel relocation in a single-pin core structure of a sodium-cooled fast reactor

Journal Article · Mon Jul 10 00:00:00 EDT 2017 · Nuclear Engineering and Design · OSTI ID:1415473

Metal fuel relocation experiments with pressure injection

Journal Article · Sat Aug 06 00:00:00 EDT 2022 · Nuclear Engineering and Design · OSTI ID:1909599

X-ray and gamma-ray tomographic imaging of fuel relocation inside sodium fast reactor test assemblies during severe accidents

Journal Article · Fri Oct 02 00:00:00 EDT 2020 · Journal of Nuclear Materials · OSTI ID:1686071

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Eutectic Formation
Metallic Fuel
Relocation
SFR

Experimental studies on metallic fuel relocation in a pin bundle core structure of a sodium-cooled fast reactor

Citation Formats

References (14)

Similar Records

Related Subjects