scholarly journals Radionuclide mass inventory, activity, decay heat, and dose rate parametric data for TRIGA spent nuclear fuels

1997 ◽  
Author(s):  
J.W. Sterbentz
Keyword(s):  
Dose Rate ◽  
Nuclear Fuels ◽  
Decay Heat ◽  
Parametric Data ◽  
Mass Inventory ◽  
Activity Decay ◽  
Inventory Activity

Impact of Approximations in Operating History Data on Spent Fuel Properties with Serpent 2

2021 ◽  
Author(s):  
Silja Häkkinen
Keyword(s):  
Spontaneous Fission ◽  
Spent Nuclear Fuel ◽  
Emission Rate ◽  
Photon Emission ◽  
Fuel Properties ◽  
Fission Rate ◽  
Decay Heat ◽  
Activity Decay ◽  
Operating History ◽  
Assembly Activity

Abstract In this work, the effect of averaging operating history parameters such as power history, boron concentration and coolant density and temperature on spent nuclear fuel properties was investigated. The examined properties were assembly activity, decay heat, photon emission rate, spontaneous fission rate and the concentration of some mobile nuclides and fissile nuclides. Calculations were performed on two similar VVER-440 fuel assemblies irradiated in different positions of the core using Serpent 2. Averaging power history over the entire irradiation history had a significant effect on assembly activity, decay heat and photon emission rate overestimating these properties approximately 70 % right after irradiation. However, the effect quickly died out and after 10 years of cooling the effect was less than 1 %. If the last cycle (3rd cycle) was modelled accurately and the power density of only the first two cycles were averaged, the differences remained always below 1 %. The effect of operating history approximations on spontaneous fission rate and the nuclide concentrations was much smaller reamaining mostly below 1.5 %. The sensitivity of nuclide concentrations to approximations in individual operating history parameters was dependent on the nuclide in question and no trend applying to all studied nuclides could be observed.

scholarly journals Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

2018 ◽  
Vol 4 ◽  
pp. 6 ◽  
Author(s):  
Dimitri A. Rochman ◽  
Alexander Vasiliev ◽  
Abdelhamid Dokhane ◽  
Hakim Ferroukhi
Keyword(s):  
Cross Sections ◽  
Power Plants ◽  
Neutron Emission ◽  
Nuclear Data ◽  
Monte Carlo Sampling ◽  
Boiling Water Reactors ◽  
Nuclear Fuels ◽  
Decay Heat ◽  
Water Reactors ◽  
The Impact

This paper presents a study of the impact of the nuclear data (cross sections, neutron emission and spectra) on different quantities for spent nuclear fuels (SNF) from Swiss power plants: activities, decay heat, neutron and gamma sources and isotopic vectors. Realistic irradiation histories are considered using validated core follow-up models based on CASMO and SIMULATE. Two Pressurized and one Boiling Water Reactors (PWR and BWR) are considered over a large number of operated cycles. All the assemblies at the end of the cycles are studied, being reloaded or finally discharged, allowing spanning over a large range of exposure (from 4 to 60 MWd/kgU for ≃9200 assembly-cycles). Both UO2 and MOX fuels were used during the reactor cycles, with enrichments from 1.9 to 4.7% for the UO2 and 2.2 to 5.8% Pu for the MOX. The SNF characteristics presented in this paper are calculated with the SNF code. The calculated uncertainties, based on the ENDF/B-VII.1 library are obtained using a simple Monte Carlo sampling method. It is demonstrated that the impact of nuclear data is relatively important (e.g. up to 17% for the decay heat), showing the necessity to consider them for safety analysis of the SNF handling and disposal.

scholarly journals The Relationship Between Dose Rate and Decay Heat for Spent Nuclear Fuel Casks

2020 ◽  
Author(s):  
Riley Cumberland ◽  
Georgeta Radulescu ◽  
Kaushik Banerjee
Keyword(s):  
Dose Rate ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Decay Heat ◽  
The Relationship
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