Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading

Technical Report · Thu Sep 01 00:00:00 EDT 2016

DOI:https://doi.org/10.2172/1325434· OSTI ID:1325434

Chandler, David ^[1]; Betzler, Ben ^[1]; Hirtz, Gregory John ^[1]; Ilas, Germina ^[1]; Sunny, Eva ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division

The purpose of this report is to document a high-fidelity VESTA/MCNP High Flux Isotope Reactor (HFIR) core model that features a new, representative experiment loading. This model, which represents the current, high-enriched uranium fuel core, will serve as a reference for low-enriched uranium conversion studies, safety-basis calculations, and other research activities. A new experiment loading model was developed to better represent current, typical experiment loadings, in comparison to the experiment loading included in the model for Cycle 400 (operated in 2004). The new experiment loading model for the flux trap target region includes full length ²⁵²Cf production targets, ⁷⁵Se production capsules, ⁶³Ni production capsules, a ¹⁸⁸W production capsule, and various materials irradiation targets. Fully loaded ²³⁸Pu production targets are modeled in eleven vertical experiment facilities located in the beryllium reflector. Other changes compared to the Cycle 400 model are the high-fidelity modeling of the fuel element side plates and the material composition of the control elements. Results obtained from the depletion simulations with the new model are presented, with a focus on time-dependent isotopic composition of irradiated fuel and single cycle isotope production metrics.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Office of Material Management and Minimization
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1325434
• Report Number(s): ORNL/TM-2016/23; TRN: US1700073
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NICKEL 63
PLUTONIUM 238
SELENIUM 75
TUNGSTEN 188
CALIFORNIUM 252
HIGHLY ENRICHED URANIUM
EXPERIMENT DESIGN
SPENT FUELS
HFIR REACTOR
REACTOR CORES
MATHEMATICAL MODELS
V CODES
M CODES
IRRADIATION CAPSULES
SIMULATION
CONTROL ELEMENTS
ISOTOPE RATIO
TIME DEPENDENCE
ISOTOPE PRODUCTION
CONVERSION
SLIGHTLY ENRICHED URANIUM
NEUTRON FLUX
PLATES
SAFETY
TRAPS
neutronics
depletion
M&S
representative
experiments