Hybrid fusion–fission reactor with a thorium blanket: Its potential in the fuel cycle of nuclear reactors

Journal Article · Tue Dec 15 04:00:00 EST 2015 · Physics of Atomic Nuclei

DOI:https://doi.org/10.1134/S1063778815100117· OSTI ID:22471976

Discussions are currently going on as to whether it is suitable to employ thorium in the nuclear fuel cycle. This work demonstrates that the {sup 231}Pa–{sup 232}U–{sup 233}U–Th composition to be produced in the thorium blanket of a hybrid thermonuclear reactor (HTR) as a fuel for light-water reactors opens up the possibility of achieving high, up to 30% of heavy metals (HM), or even ultrahigh fuel burnup. This is because the above fuel composition is able to stabilize its neutron-multiplying properties in the process of high fuel burnup. In addition, it allows the nuclear fuel cycle (NFC) to be better protected against unauthorized proliferation of fissile materials owing to an unprecedentedly large fraction of {sup 232}U (several percent!) in the uranium bred from the Th blanket, which will substantially hamper the use of fissile materials in a closed NFC for purposes other than power production.

• OSTI ID: 22471976
• Journal Information: Physics of Atomic Nuclei, Journal Name: Physics of Atomic Nuclei Journal Issue: 10 Vol. 78; ISSN 1063-7788; ISSN PANUEO
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
BREEDING BLANKETS
BURNUP
FISSILE MATERIALS
FISSION
FUEL CYCLE
NUCLEAR FUELS
PROTACTINIUM 231
THERMONUCLEAR REACTORS
THORIUM
URANIUM
URANIUM 232
URANIUM 233
WATER COOLED REACTORS
WATER MODERATED REACTORS