Preliminary Conceptual Design of Nuclear Thermal Rocket Reactor Cores Using Ceramic Fuels with Beryllium or Composite Neutron Moderators

Youinou, Gilles J.; Abou-Jaoudé, Abdalla

doi:10.1080/00295639.2023.2252637

Preliminary Conceptual Design of Nuclear Thermal Rocket Reactor Cores Using Ceramic Fuels with Beryllium or Composite Neutron Moderators

Journal Article · Thu Oct 12 00:00:00 EDT 2023 · Nuclear Science and Engineering

DOI:https://doi.org/10.1080/00295639.2023.2252637· OSTI ID:2228929

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Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Herein several preliminary conceptual designs of nuclear thermal rocket reactor cores are presented that use tin-bonded monolithic ceramic [mononitride (UN), monocarbide (UC), and uranium dioxide (UO₂)] fuel plates or pins with molybdenum-tungsten alloy clad. Neutron moderation is provided by a block of Be metal or composite materials using metal hydrides such as ZrH_1.6 or YH_1.6 with different matrices (MgO or Be). Mainly high-assay low-enriched uranium is considered, but highly enriched uranium is also assessed for a few configurations. Nominal core thermal power is 300 MW corresponding to about 66 kN (15 klbf) of thrust, and with minimal modifications, 500 MW may be possible (25 klbf of thrust). Depending on the configurations, the amount of ²³⁵U needed for criticality is 30 to 90 kg, and reactor weight is 2.5 to 3.8 tonnes.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA); USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2228929

Report Number(s):: INL/JOU--23-71128-Rev000

Journal Information:: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 8 Vol. 198; ISSN 0029-5639

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

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