Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5
Graph Chatbot
Chat with Graph Search
Ask any question about EPFL courses, lectures, exercises, research, news, etc. or try the example questions below.
DISCLAIMER: The Graph Chatbot is not programmed to provide explicit or categorical answers to your questions. Rather, it transforms your questions into API requests that are distributed across the various IT services officially administered by EPFL. Its purpose is solely to collect and recommend relevant references to content that you can explore to help you answer your questions.
The present doctoral research aims at the appraisal of nodal core simulators used for the calculation of commercial boiling water reactor (BWR) cores, against measurements carried out at the Paul Scherrer Institute under the LWR-PROTEUS experimental progra ...
The LWR-PROTEUS Phase II experimental program was conducted at the Proteus research reactor at the Paul Scherrer Institute (PSI) in the early 2000s. One of its purposes was to gain more insight into the reactivity changes caused by fuel burnup and to devel ...
A room temperature ionic liquid (IL) composed of a quaternary alkylphosphonium (trihexyltetradecylphosphonium, P66614(+)) and tetrakis(pentafluorophenyl) borate anion (TB) was employed within a water| P66614TB (w|P66614TB or w|IL) biphasic system to evalua ...
The interactions of trivalent lanthanides and actinides with secondary mineral phases such as calcite is of high importance for the safety assessment of deep geological repositories for high level nuclear waste (HLW). Due to similar ionic radii, calcium-be ...
This paper presents an assessment conducted at the Paul Scherrer Institut (PSI) of two Monte Carlo-based codes, namely Monteburns and Serpent, for LWR depletion calculations. First, a validation of predicted spent fuel compositions is presented on the basi ...
In today's applied light water reactor (LWR) technology, the fissile material is embedded in a ceramic matrix, pressed, and sintered to pellets, which are then filled into the cladding tube of fuel pins that are assembled to a fuel bundle. This is the most ...
Decomposition into higher species: Intramolecular UIII-mediated homolytic C-O bond cleavage in UIII (alkoxy)siloxy complexes at low temperature and subsequent reduction with KC8 led to unprecedented polymetallic complexes containing siloxy, silanediolate, ...
Based on closed packed microspheres produced by internal gelation, the Sphere-pac concept provides a safer and cleaner process and better remote production capability compared to the traditional production of nuclear fuels. Whereas classical reactor fuel r ...
In recent years, higher discharge burn-ups and initial fuel enrichments have led to more and more heterogeneous core configurations in light water reactors (LWRs), especially at the beginning of cycle when fresh fuel assemblies are loaded next to highly bu ...
A BaCO3 slurry, containing radioactive C-14, is produced during the reprocessing of spent nuclear fuel. This slurry is encapsulated in a Portland-blastfurnace slag composite cement. The effect of BaCO3 on the hydration of OPC and Portland-blastfurnace slag ...