Zobrazeno 1 - 10
of 10
pro vyhledávání: '"Cole Blakely"'
Publikováno v:
Annals of Nuclear Energy. 122:8-22
The LOCA Toolkit for U.S. light water reactors (LOTUS) currently under development at Idaho National Labs (INL) is a plug and play, multiphysics environment to be used in support of system level plant transient analysis. New proposed rule changes in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fd3d69f049a2f04794a508c114c2e2ed
https://doi.org/10.1016/j.anucene.2018.08.027
https://doi.org/10.1016/j.anucene.2018.08.027
Publikováno v:
Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation.
Extending the fuel discharge burnup level, e.g., from the current limit of rod averaged discharge burnup limit of 62 GWD/MT to a proposed new limit of 75 GWD/MT, can provide significant economic benefits to the current fleet of operating light water
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a5c1a18b26e6d8f5b1fee4f11ab9b4fb
https://doi.org/10.1115/icone2020-16098
https://doi.org/10.1115/icone2020-16098
Publikováno v:
Nuclear Engineering and Design. 332:186-201
Uncertainty quantification (UQ) and sensitivity analyses (SA) are performed for coupled simulations between VERA-CS, a coupled pin resolved neutron transport and subchannel thermal hydraulics code, and the fuel performance code BISON. The interface b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54f0850d0219171179f9913b54001718
https://doi.org/10.1016/j.nucengdes.2018.03.023
https://doi.org/10.1016/j.nucengdes.2018.03.023
Publikováno v:
Annals of Nuclear Energy. 111:683-701
A demonstration and description of the LOCA Toolkit for US light water reactors (LOTUS) is presented. Through LOTUS, the core simulator VERA-CS developed by CASL is coupled with the fuel performance code FRAPCON. The coupling is performed with consis
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::155c3d1e23b1ed97d8562b1745336a76
https://doi.org/10.1016/j.anucene.2017.09.029
https://doi.org/10.1016/j.anucene.2017.09.029
Publikováno v:
Journal of Nuclear Materials. 553:153037
Accident tolerant fuels (ATFs) such as FeCrAl cladding have been designed to have improved performance in normal operation and provide increased coping time during design basis accidents (DBA) and beyond DBA. A key aspect in the evaluation of ATF des
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f60466afb898aac99452cec5ad7e40d1
https://doi.org/10.1016/j.jnucmat.2021.153037
https://doi.org/10.1016/j.jnucmat.2021.153037
Publikováno v:
Nuclear Engineering and Design. 376:111132
Increasing the burnup limit from 62 GWd/MTU to 75 GWd/MTU can help increase the cycle length of a typical pressurized water reactor from 18 months to two years or longer. To meet this goal, the fuel enrichment limit must also be increased from 5.0 w/
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::634da56654075e860d843ab2d748acf0
https://doi.org/10.1016/j.nucengdes.2021.111132
https://doi.org/10.1016/j.nucengdes.2021.111132
Publikováno v:
46th AIAA Fluid Dynamics Conference.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1f324cdb6fae3c9756353c85730e5ea
https://doi.org/10.2514/6.2016-3351
https://doi.org/10.2514/6.2016-3351
Publikováno v:
54th AIAA Aerospace Sciences Meeting.
In this work, we examine a two-equation turbulence model in the flux correction method for three-dimensional turbulent flows on strand grids. Building upon previous work, flux derivatives along strands are treated with high-order summation-by-parts o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::39540a256f7708fd747e77f8fa06e30d
https://doi.org/10.2514/6.2016-1582
https://doi.org/10.2514/6.2016-1582