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

Abstract

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.

Authors:
 [1];  [1];  [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA), Office of Material Management and Minimization
OSTI Identifier:
1325434
Report Number(s):
ORNL/TM-2016/23
TRN: US1700073
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
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

Citation Formats

Chandler, David, Betzler, Ben, Hirtz, Gregory John, Ilas, Germina, and Sunny, Eva. Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading. United States: N. p., 2016. Web. doi:10.2172/1325434.
Chandler, David, Betzler, Ben, Hirtz, Gregory John, Ilas, Germina, & Sunny, Eva. Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading. United States. https://doi.org/10.2172/1325434
Chandler, David, Betzler, Ben, Hirtz, Gregory John, Ilas, Germina, and Sunny, Eva. 2016. "Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading". United States. https://doi.org/10.2172/1325434. https://www.osti.gov/servlets/purl/1325434.
@article{osti_1325434,
title = {Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading},
author = {Chandler, David and Betzler, Ben and Hirtz, Gregory John and Ilas, Germina and Sunny, Eva},
abstractNote = {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.},
doi = {10.2172/1325434},
url = {https://www.osti.gov/biblio/1325434}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {9}
}