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

Journal Article · 12 October 2023 · Nuclear Science and Engineering

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

Youinou, Gilles J.  ^[1]; Abou-Jaoudé, Abdalla  ^[1]

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1. 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.

• 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; TRN: US2407418
• Journal Information: Nuclear Science and Engineering, Vol. 198, Issue 8; ISSN 0029-5639
• Publisher: Taylor & FrancisCopyright Statement
• Country of Publication: United States
• Language: English