Aqueous leaching of high burnup UO2 fuel under hydrogen conditions

MRS Advances ◽  
2018 ◽  
Vol 3 (19) ◽  
pp. 1013-1018 ◽  
Author(s):  
Anders Puranen ◽  
Olivia Roth ◽  
Lena Z. Evins ◽  
Kastriot Spahiu
Keyword(s):  
Nuclear Fuel ◽  
Hydrogen Pressure ◽  
Spent Nuclear Fuel ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Fuel Layer ◽  
Initial Release ◽  
Radionuclide Inventory ◽  
High Burnup ◽  
Granitic Groundwater

ABSTRACTLeaching results on fragments of high burnup (65 MWd/kgU) UO2 fuel from a commercial pressurized water reactor are presented. The experiment was performed in simplified granitic groundwater under a hydrogen pressure of up to 5 MPa, representing conditions in a water intrusion scenario for a Swedish KBS-3 design spent nuclear fuel repository. The freshly crushed fragments were pre-washed for 6 days to remove pre-oxidized matrix and part of the instant release fraction of the radionuclide inventory, and then transferred to an autoclave for leaching under hydrogen conditions. Following an initial release of U attributed to dissolution of a pre-oxidized fuel layer caused by the aerated handling mainly during the transfer from pre-washing to autoclave, the U concentration decreased with time to levels of 2-5x10-9 M, which corresponds, approximately, to the solubility of amorphous UO2. The release of radionuclides such as Cs and Sr gradually declined indicating a transition to inhibition of the fuel matrix dissolution.

scholarly journals Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code

Data in Brief ◽  
2020 ◽  
Vol 33 ◽  
pp. 106429
Author(s):  
Zsolt Elter ◽  
Li Pöder Balkeståhl ◽  
Erik Branger ◽  
Sophie Grape
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Data Library

Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel—I: Methodology Overview

1999 ◽  
Vol 125 (3) ◽  
pp. 255-270 ◽  
Author(s):  
Dale B. Lancaster ◽  
Emilio Fuentes ◽  
Chi H. Kang ◽  
Meraj Rahimi
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory

2018 ◽  
Vol 120 ◽  
pp. 431-449 ◽  
Author(s):  
Bamidele Ebiwonjumi ◽  
Sooyoung Choi ◽  
Matthieu Lemaire ◽  
Deokjung Lee ◽  
Ho Cheol Shin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

Study of the release of the fission gases (Xe and Kr) and the fission products (Cs and I) under anoxic conditions in bicarbonate water

2015 ◽  
Vol 1744 ◽  
pp. 35-41 ◽  
Author(s):  
Ernesto González-Robles ◽  
Markus Fuß ◽  
Elke Bohnert ◽  
Nikolaus Müller ◽  
Michel Herm ◽  
...  
Keyword(s):  
Gas Phase ◽  
Nuclear Fuel ◽  
Safety Assessment ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Collaborative Project ◽  
Fuel Rod ◽  
Release Ratio

ABSTRACTFor safety assessment analyses of the disposal of spent nuclear fuel (SNF) in deep geological repositories it is indispensable to evaluate the contribution of fission products to the instant release fraction (IRF). During the last three years the EURATOM FP7 Collaborative Project, “Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel (CP FIRST-Nuclides)” was carried out to get a better understanding of the IRF.Within CP FIRST-Nuclides, a leaching experiment with a cladded SNF pellet was performed in bicarbonate water (19 mM NaCl + 1 mM NaHCO3) under Ar /H2 atmosphere over 333 days. The cladded SNF pellet was obtained from a fuel rod segment which was irradiated in the Gösgen pressurized water reactor; the average burn-up of the segment was 50.4 MWd/kgUO2. In the multi-sampling experiment, gaseous and liquid samples were taken periodically. The moles of the fission gases Kr and Xe released in the gas phase and those of 129I and 137Cs released in solution were measured. Cumulative release fractions of (1.6 ± 0.2)·10-1 fission gases, (1.6 ± 0.1)·10-1129I and (3.9 ± 0.2)·10-2 137Cs, respectively, were achieved after 333 days of leaching. Accordingly the release ratio of fission gases to 129I was 1:1 and the release ratio of fission gases to 137Cs was 4:1, respectively.

scholarly journals Fatigue Behavior of Spent Nuclear Fuel Rods in Simulated Transportation Environment

2017 ◽  
Author(s):  
Hong Wang ◽  
Jy-an John Wang ◽  
Hao Jiang
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fatigue Behavior ◽  
The United States ◽  
Pressurized Water ◽  
Fuel Rods ◽  
Cyclic Bending ◽  
Oak Ridge ◽  
High Burnup ◽  
Reversed Cyclic

Nuclear fuel rod is composed of cladding tube and a specified number of fuel pellets contained. In the United States, spent nuclear fuel (SNF) is expected to be transported to at least one storage facility before permanent disposal. The fatigue behavior of spent nuclear fuel (SNF) rods under reversed cyclic bending must be understood in order to evaluate their vibration integrity in a transportation environment. This is especially important for high-burnup SNFs (>45 GWd/MTU). This report presents the experimental results related to Zircaloy (Zry)-4-based surrogate rods and high-burnup SNFs, based on recent work performed at Oak Ridge National Laboratory (ORNL). The surrogate rod was made of Zry-4 cladding and alumina pellets, and high-burnup fuel rods were discharged from H.B. Robinson pressurized water reactor. The reversed cyclic bending testing was conducted at 5 Hz under loading control. The effect of pre-hydriding and burnup or irradiation on the flexural rigidity and fatigue life of cladding-pellet system were discussed. The fatigue data obtained are extremely useful to the future certification of SNF storage and transportation cask.

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