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|a (TOE)ost1340461
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|a (TOE)1340461
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|a E 1.99:ornl/tm-2016/742
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|a E 1.99:ornl/tm-2016/742
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|a ornl/tm-2016/742
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|a Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor
|h [electronic resource]
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|a Washington, D.C. :
|b United States. Office of the Assistant Secretary for Nuclear Energy ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 2017.
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| 300 |
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|a 46 p. :
|b digital, PDF file.
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| 336 |
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|a text
|b txt
|2 rdacontent.
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|a computer
|b c
|2 rdamedia.
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| 338 |
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|a online resource
|b cr
|2 rdacarrier.
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|a Published through SciTech Connect.
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|a 01/15/2017.
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| 500 |
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|a "ornl/tm-2016/742"
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|a Benjamin R. Betzler; Jeffrey J. Powers; Andrew Worrall; Sean Robertson; Leslie Dewan; Mark Massie.
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|a This status report presents the results from the first phase of the collaboration between Transatomic Power Corporation (TAP) and Oak Ridge National Laboratory (ORNL) to provide neutronic and fuel cycle analysis of the TAP core design through the Department of Energy Gateway for Accelerated Innovation in Nuclear, Nuclear Energy Voucher program. The TAP design is a molten salt reactor using movable moderator rods to shift the neutron spectrum in the core from mostly epithermal at beginning of life to thermal at end of life. Additional developments in the ChemTriton modeling and simulation tool provide the critical moderator-to-fuel ratio searches and time-dependent parameters necessary to simulate the continuously changing physics in this complex system. Results from simulations with these tools show agreement with TAP-calculated performance metrics for core lifetime, discharge burnup, and salt volume fraction, verifying the viability of reducing actinide waste production with this design. Additional analyses of time step sizes, mass feed rates and enrichments, and isotopic removals provide additional information to make informed design decisions. This work further demonstrates capabilities of ORNL modeling and simulation tools for analysis of molten salt reactor designs and strongly positions this effort for the upcoming three-dimensional core analysis.
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|b AC05-00OR22725.
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|a Reactor Design.
|2 local.
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| 650 |
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|a Molten Salt Reactors.
|2 local.
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| 650 |
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|a Computerized Simulation.
|2 local.
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| 650 |
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|a Nuclear Fuels.
|2 local.
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| 650 |
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|a Reactor Kinetics.
|2 local.
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|a Fuel Cycle.
|2 local.
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| 650 |
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|a Neutron Spectra.
|2 local.
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|a Spectral Shift.
|2 local.
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|a Time Dependence.
|2 local.
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| 650 |
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|a Two-Dimensional Calculations.
|2 local.
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| 650 |
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|a Moderators.
|2 local.
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| 650 |
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|a Burnup.
|2 local.
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| 650 |
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|a Enrichment.
|2 local.
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| 650 |
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|a Lifetime.
|2 local.
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| 650 |
|
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|a Performance.
|2 local.
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| 650 |
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|a Reactor Cores.
|2 local.
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| 650 |
|
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|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
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| 710 |
2 |
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|a Oak Ridge National Laboratory.
|4 res.
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| 710 |
1 |
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|a United States.
|b Office of the Assistant Secretary for Nuclear Energy.
|4 spn.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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| 856 |
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|u http://www.osti.gov/scitech/biblio/1340461
|z Full Text (via OSTI)
|
| 907 |
|
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|a .b90368289
|b 11-29-21
|c 02-15-17
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| 998 |
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|a web
|b 10-03-19
|c f
|d m
|e p
|f eng
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|h 0
|i 3
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|s eacde8b3-72e2-53ce-8f7d-38126fb48740
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| 952 |
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:ornl/tm-2016/742
|h Superintendent of Documents classification
|i web
|n 1
|
