Category of Content

Siting Experience Documents Only

Publication Date

Keywords

Displaying 1 - 25 of 61

Isotopic Analysis of High-Burnup PWR Spent Fuel Samples from the Takahama-3 Reactor

Isotopic Analysis of High-Burnup PWR Spent Fuel Samples from the Takahama-3 Reactor

Author(s)
Gauld, I. C. ,
Sanders, C. E.
Publication Date

This report presents the results of computer code benchmark simulations against spent fuel radiochemical assay
measurements from the Kansai Electric Ltd. Takahama-3 reactor published by the Japan Atomic Energy
Research Institute. Takahama-3 is a pressurized-water reactor that operates with a 17 × 17 fuel-assembly design.
Spent fuel samples were obtained from assemblies operated for 2 and 3 cycles and achieved a maximum burnup
of 47 GWd/MTU. Radiochemical analyses were performed on two rods having an initial enrichment of

burnup credit criticality analysis nureg/cr-6798 ornl/tm-2001/259 spent fuel composition

Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation

Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation

Author(s)
Lancaster, D.
Publication Date

Pressurized water reactor (PWR) burnup credit validation is
demonstrated using the benchmarks for quantifying fuel reactivity
decrements, published as Benchmarks for Quantifying Fuel Reactivity
Depletion Uncertainty, Electric Power Research Institute (EPRI)
report 1022909. This demonstration uses the depletion module
TRITON (Transport Rigor Implemented with Time-Dependent
Operation for Neutronic Depletion) available in the SCALE 6.1
(Standardized Computer Analyses for Licensing Evaluations) code

burnup credit spent fuel fission products criticality analysis keff validation epri tr 1025203 spent fuel composition used fuel

Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation--Calvert Cliffs, Takahama, and Three Mile Island Reactors

Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation--Calvert Cliffs, Takahama, and Three Mile Island Reactors

Author(s)
Ilas, G. ,
Gauld, I. C. ,
Difilippo, F. C. ,
Emmett, M. B.
Publication Date

This report is part of a report series designed to document benchmark-quality radiochemical isotopic
assay data against which computer code accuracy can be quantified to establish the uncertainty and bias
associated with the code predictions. The experimental data included in the report series were acquired
from domestic and international programs and include spent fuel samples that cover a large burnup range.
The measurements analyzed in the current report, for which experimental data is publicly available,

burnup credit spent fuel criticality analysis spent fuel composition nureg/cr-6968 ornl/tm-2008/071 used fuel

Burn-up Credit Criticality Safety Benchmark - Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal

Burn-up Credit Criticality Safety Benchmark - Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal

Author(s)
Wagner, J. C. ,
Radulescu, G.
Publication Date
burnup credit spent fuel isbn 978-92-64-99172-9 nea no. 6998 criticality analysis spent fuel composition nea wpncs egbuc used fuel

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

Author(s)
Solis, J.
Publication Date

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

slides nei used fuel management meeting cfd thermal modeling vacuum drying
Disclaimer: Note that this page contains links to external sites. When leaving the CURIE site, please note that the U.S. Department of Energy and Pacific Northwest National Laboratory do not control or endorse the content or ads on these sites.
Sponsored by: