Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor. (September 2018)
- Record Type:
- Journal Article
- Title:
- Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor. (September 2018)
- Main Title:
- Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor
- Authors:
- Li, G.C.
Cong, P.
Yu, C.G.
Zou, Y.
Sun, J.Y.
Chen, J.G.
Xu, H.J. - Abstract:
- Abstract: Molten salt reactor (MSR) shows great promise of high thermal-electric conversion efficiency, inherent safety, and on-line reprocessing. Furthermore, fuel breeding can be realized in both thermal and fast spectrum reactors with Th-U fuel cycle, which can make use of the abundant resource of thorium. In order to combine the advantages of high breeding ratio (BR) in fast spectrum and low fissile inventory for criticality in thermal spectrum, a single-fluid double-zone thorium-based molten salt reactor (SD-TMSR) core configuration is proposed. First, assemblies in both the inner and the outer zones are optimized by adjusting the ratios of molten salt and graphite with consideration of BR, 233 U inventory, double time (DT), and temperature coefficient of reactivity (TCR) at the startup time, aiming to have a minimal DT for fuel breeding and a negative TCR for security. The results show that DT has the optimum value when the ratios of molten salt and graphite in the inner zone and the outer zone are 0.357 and 1.162, respectively. And the TCR can be improved to −2 pcm/K when the side length of the graphite hexagonal prism is 7.5 cm. Then, based on the optimized geometry, the burn-up calculations with a series of on-line reprocessing rates are carried out with a self-developed MSR reprocessing sequence (MSR-RS). The results show that on-line reprocessing is beneficial to the Th-U fuel breeding. When the reprocessing rate is 200 l/d, iso-breeding can be achieved. When theAbstract: Molten salt reactor (MSR) shows great promise of high thermal-electric conversion efficiency, inherent safety, and on-line reprocessing. Furthermore, fuel breeding can be realized in both thermal and fast spectrum reactors with Th-U fuel cycle, which can make use of the abundant resource of thorium. In order to combine the advantages of high breeding ratio (BR) in fast spectrum and low fissile inventory for criticality in thermal spectrum, a single-fluid double-zone thorium-based molten salt reactor (SD-TMSR) core configuration is proposed. First, assemblies in both the inner and the outer zones are optimized by adjusting the ratios of molten salt and graphite with consideration of BR, 233 U inventory, double time (DT), and temperature coefficient of reactivity (TCR) at the startup time, aiming to have a minimal DT for fuel breeding and a negative TCR for security. The results show that DT has the optimum value when the ratios of molten salt and graphite in the inner zone and the outer zone are 0.357 and 1.162, respectively. And the TCR can be improved to −2 pcm/K when the side length of the graphite hexagonal prism is 7.5 cm. Then, based on the optimized geometry, the burn-up calculations with a series of on-line reprocessing rates are carried out with a self-developed MSR reprocessing sequence (MSR-RS). The results show that on-line reprocessing is beneficial to the Th-U fuel breeding. When the reprocessing rate is 200 l/d, iso-breeding can be achieved. When the reprocessing rate is 5 m 3 /d, the performance of Th-U breeding is improved significantly, and only 16 years is needed for the 233 U doubling. The results also show that TCR remains negative and inherent safety is satisfied during all the operation time. Graphical abstract: Image 1 … (more)
- Is Part Of:
- Progress in nuclear energy. Volume 108(2018)
- Journal:
- Progress in nuclear energy
- Issue:
- Volume 108(2018)
- Issue Display:
- Volume 108, Issue 2018 (2018)
- Year:
- 2018
- Volume:
- 108
- Issue:
- 2018
- Issue Sort Value:
- 2018-0108-2018-0000
- Page Start:
- 144
- Page End:
- 151
- Publication Date:
- 2018-09
- Subjects:
- Molten salt reactor -- Neutronics and modeling -- Th-U fuel breeding
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
333.7924 - Journal URLs:
- http://www.sciencedirect.com/science/journal/01491970 ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.pnucene.2018.04.017 ↗
- Languages:
- English
- ISSNs:
- 0149-1970
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 6870.542000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 17948.xml