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Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uranium
- Source :
- Nuclear Engineering and Technology, Vol 56, Iss 12, Pp 5330-5338 (2024)
- Publication Year :
- 2024
- Publisher :
- Elsevier, 2024.
-
Abstract
- The space nuclear reactor cooled by heat pipes has become the preferred choice for future space missions and deep space exploration missions. The use of low-enriched uranium (LEU) is promoted to achieve the goal of nuclear non-proliferation worldwide. In this study, a lithium heat pipe cooled space reactor with LEU (HP-LEU) was proposed based on Heat Pipes-Segmented Thermoelectric Module Converters (HP-STMCs), with the addition of moderators. The HP-LEU employs yttrium hydride (YH2) as the moderator and 19.9 % enriched uranium nitride (UN) as the fuel. The neutronics analysis has been performed on the HP-LEU reactor and the results have showed that the HP-LEU has a lifetime of more than 12 years. Two control systems have been applied in the reactor and have demonstrated the capacity to independently regulate and shut down the reactor. The total temperature reactivity coefficients are consistently negative, indicating that the HP-LEU reactor is inherently safe during operation. During normal operation, the temperatures of the materials are all acceptable. This study can serve as a reference for lithium heat pipe cooled space reactors with LEU.
Details
- Language :
- English
- ISSN :
- 17385733
- Volume :
- 56
- Issue :
- 12
- Database :
- Directory of Open Access Journals
- Journal :
- Nuclear Engineering and Technology
- Publication Type :
- Academic Journal
- Accession number :
- edsdoj.4a49f854251a4145a43f0f3eff3803a2
- Document Type :
- article
- Full Text :
- https://doi.org/10.1016/j.net.2024.07.042