Preliminary conceptual design of fast neutron spectrum nuclear thermal rocket cores using monolithic uranium nitride fuel

Journal Article · Fri Jul 01 00:00:00 EDT 2022 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2022.104237· OSTI ID:1872986

Youinou, Gilles J. ^[1]; Lin, Ching-Sheng ^[2]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States
2. Idaho National Lab. (INL), Idaho Falls, ID (United States)

This paper presents a few nuclear thermal rocket (NTR) reactor core preliminary conceptual designs based on the use of monolithic uranium nitride (UN) fuel plates or pins clad with tungsten (W), alloyed or unalloyed as needed. High-assay low-enriched uranium (HALEU) as well as high-enriched uranium (HEU) are considered. Nominal core thermal powers are between 300 and 1100 MW corresponding to thrusts between 66 kN and 240 kN. The estimated thrust-to-reactor-weight ratios (T/WRx) achievable with the HEU plate and pin configurations are between 3.8 and 10.9. The T/WRx achievable with the HALEU plate and pin configurations are lower, 1.9–4.0, than those achievable with HEU. It is noteworthy that even a relatively modest increase in fuel enrichment above the HALEU limit enables a significant increase in T/WRx. It must be emphasized that these results do not yet account for uncertainties and that the appropriateness of the assumed fuel thermal design limits for normal operation (i.e., peak centerline temperature of 3100 K) will need to be confirmed. Finally, just like for the other UN-based fuels currently considered for NTR applications (i.e., CERMET and CERCER), the proposed UN fuel systems need significant testing in prototypic conditions to confirm the appropriate performance for safe NTR applications. However, the monolithic fuel systems may have, overall, a higher technology readiness level (TRL), and, consequently, shorter fuel development and validation time may result.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: NASA; USDOE Office of Nuclear Energy (NE)
• Grant/Contract Number: AC07-05ID14517
• OSTI ID: 1872986
• Report Number(s): INL/JOU-21-64551-Rev000
• Journal Information: Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Journal Issue: - Vol. 149; ISSN 0149-1970
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
33 ADVANCED PROPULSION SYSTEMS
Fast Neutron Spectrum
Nuclear Thermal Propulsion
Uranium Nitride