Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient

2021 ◽  
Vol 544 ◽  
pp. 152711
Author(s):  
Fidelma G. Di Lemma ◽  
Karen E. Wright ◽  
Luca Capriotti ◽  
Adam X. Zabriskie ◽  
Alexander J. Winston ◽  
...  
Keyword(s):  
Author(s):  
Taide Tan ◽  
Randy Clarksean ◽  
Yitung Chen ◽  
Darrell Pepper ◽  
Mitchell K. Meyer

The filling and solidification process for melt casting a metallic fuel pin is considered. The problem was analyzed numerically using the commercial finite element software package FIDAP (Fluent, Inc.). Numerical simulations are performed to study process parameters that could impact the solidification of the melt within the mold. A Metallic Fuel Pin mold is a long, thin, straw-like pipe, which has a cylindrical shape. The fluid is a high-temperature melt mixture of Am, Pu, and Zr. which is considered as an incompressible Newtonian fluid. Filling velocities and filling pressures are varied to study what impact these parameters might have on flow and solidification within the melt.


Energies ◽  
2021 ◽  
Vol 14 (2) ◽  
pp. 515
Author(s):  
Kyle M. Paaren ◽  
Nancy Lybeck ◽  
Kun Mo ◽  
Pavel Medvedev ◽  
Douglas Porter

BISON finite element method fuel performance simulations were conducted using an existing automated process that couples the Fuels Irradiation & Physics Database (FIPD) and the Integral Fast Reactor Materials Information System database by writing input files and comparing the BISON output to post-irradiation fuel pin profilometry measurements contained within the databases. The importance of this work is to demonstrate the ability to benchmark fuel performance metallic fuel models within BISON using Experimental Breeder Reactor-II fuel pin data for a number of similar pins, while building off previous modeling efforts. Changes to the generic BISON input file include implementing pin specific axial power and flux profiles, pin specific fluences, frictional contact, and irradiation-induced volumetric swelling models for cladding. A statistical analysis of irradiation-induced volumetric swelling models for HT9, D9, and SS316 was performed for experiments X421/X421A, X441/X441A, and X486. Between these three experiments, there were 174 post-irradiation examination (PIE) profilometries used for validating the swelling models presented using a standard error of the estimate (SEE) method. Implementation of the volumetric swelling models for D9 and SS316 claddings was found to have a significant impact on the BISON profilometry simulated, where HT9 clad pins had an insignificant change due to low fluence values. BISON profilometry simulated for HT9, D9, and SS316 fuel pins agreed with PIE profilometry measurements, with assembly SEE values being 4.4 × 10−3 for X421A, 2.0 × 10−3 for X441A, and 2.8 × 10−3 for X486. D9 clad pins in X421/X421A had the highest SEE values, which is due to the BISON simulated profilometry being shifted axially. While this work accomplished its purpose to demonstrate the modeling of multiple fuel pins from the databases to help validate models, the results suggest that the continued development of metallic fuel models is necessary for qualifying new metallic fuel systems to better capture some physical performance phenomena, such as the hot pressing of U-Pu-Zr and the fuel cladding chemical interaction.


Author(s):  
V. A. Poryazov ◽  
◽  
O. G. Glotov ◽  
V. A. Arkhipov ◽  
G. S. Surodin ◽  
...  

The goal of this research is to obtain experimental information about combustion characteristics of the composite propellant containing various metallic fuels. The propellant formulations contained two fractions of ammonium perchlorate (64.6%), inert binder (19.7%) - butadiene rubber SKD plastized with transformer oil, and metal fuel (15.7% of aluminum ASD-4, ASD-6, Alex; boron; aluminum diboride; aluminum dodecaboride; some mixtures of above listed ingredients). Experimental information will be used further as a background to develop the physical and mathematical model of combustion process.


Author(s):  
Benjamin A. Lindley ◽  
N. Zara Zainuddin ◽  
Fausto Franceschini ◽  
Geoffrey T. Parks

It is difficult to perform multiple recycle of transuranic (TRU) isotopes in PWRs as the moderator temperature coefficient (MTC) tends to become positive after a few recycles and the core may have positive reactivity when fully voided. Due to the favorable impact on the MTC and void coefficient fostered by use of thorium (Th), the possibility of performing Th-TRU multiple-recycle in reduced-moderation PWRs (RMPWRs) is under consideration. The simplest way to reduce the moderation in a PWR is to increase the fuel pin diameter. This configuration improves the trade-off between achievable burn-up and MTC, but is ultimately limited by thermal-hydraulic constraints. Heterogeneous recycle with the bred uranium (U3) and the TRU are arranged in separate pins was found to be neutronically preferable to a homogeneous configuration. Spatial separation also enables the U3 and TRU to be refueled on different batch schemes. These techniques allow satisfactory discharge burn-up while ensuring negative MTC and fully voided reactivity, with the pin diameter of a standard PWR increased from 9.5 mm to 11 mm. Reactivity control is a key challenge due to the reduced worth of neutron absorbers and their detrimental effect on the void coefficients, especially when diluted, as is the case for soluble boron. It seems necessary to control the core using control rods to keep the fully voided reactivity negative. A preliminary analysis indicates that this is feasible.


Atomic Energy ◽  
1992 ◽  
Vol 72 (6) ◽  
pp. 545-547
Author(s):  
Yu. P. Malers
Keyword(s):  

2021 ◽  
Vol 382 ◽  
pp. 111372
Author(s):  
Abhitab Bachchan ◽  
K. Devan ◽  
K. Yernamma ◽  
M. Alagan ◽  
K. Natesan ◽  
...  
Keyword(s):  

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