Applicability evaluation to a MOX fueled fast breeder reactor for a self-consistent nuclear energy system
| Autor: | Kobayashi Kaoru, M. Ohashi, Masaki Saito, K. Kawashima, Y. Fujii-e, A. Tohkura |
|---|---|
| Rok vydání: | 1998 |
| Předmět: |
Nuclear fission product
Nuclear fuel Nuclear transmutation Nuclear engineering Energy Engineering and Power Technology Nuclear reactor Spent nuclear fuel law.invention Nuclear Energy and Engineering law Breeder reactor Environmental science Safety Risk Reliability and Quality Waste Management and Disposal MOX fuel Burnup |
| Zdroj: | Progress in Nuclear Energy. 32:681-688 |
| ISSN: | 0149-1970 |
| DOI: | 10.1016/s0149-1970(97)00080-2 |
| Popis: | The potential for a MOX fueled fast breeder reactor (FBR) is evaluated with regard to its ability to transmute radioactive nuclides and its safety when incorporated in a self-consistent nuclear energy system (SCNES). The FBR's annual production amounts of selected long-lived fission products (LLFPs), Se-79, Tc-99, Pd-107, I-129, Cs-135 and Sm-151, can be transmuted by using a two layer radial blanket region without a significant impact on core nuclear and safety characteristics. The other LLFPs are confined in the system. The hazard index level of the LLFPs per one ton of spent fuel from the system after 10 2 years is as small as that of a typical uranium ore. Regarding self-controllability in the system's safety, the proposed FBR core concept has an inherent negative reactivity feedback with a gas expansion module, sodium plenum above the core and burnup reactivity compensation module. So sodium boiling and fuel melting will be avoided in anticipated transient without scram events. Regarding self-terminability, even if the MOX fuel melting should cause a core compaction process, re-criticality of the core can be avoided by a fuel dilution and relocation module. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|
Full Text from ScienceDirect