Published November 2018
| Version v1
Journal article
Impacts of 240Pu self-shielding effect and uncertainties of σ(n,γ) at resonance energy on the reactivity controllability in HTGR inert matrix fuel
- 1. Tokyo Institute of Technology, Tokyo (Japan)
Description
The resonance (n,γ) reaction of 240Pu is one of dominant phenomena to the self-shielding effect and the reactivity controllability in plutonium fuel for high temperature gas cooled reactors (HTGRs) aiming to deep-burning. Impacts of the mitigation of the self-shielding effect and nuclear data uncertainties for the resonance (n,γ) reaction of 240Pu on the reactivity controllability were investigated for various fuel design using MVP code. k∞ decreased from 1.3 to 1.05 and reactivity fluctuation decreased from 30% to 6% in the proposed inert matrix fuel (IMF) design with a dilution of the TRU oxide kernel and the neutron spectrum control because of mitigation of 240Pu self-shielding effect at 1.056-eV. (author)
Availability note (English)
Available from http://dx.doi.org/10.15669/pnst.5.100Additional details
Identifiers
- DOI
- 10.15669/pnst.5.100;
Publishing Information
- Journal Title
- Progress in Nuclear Science and Technology
- Journal Volume
- 5
- Journal Page Range
- p. 100-103
- ISSN
- 2185-4823
Conference
- Title
- International conference on science and technology of actinide and transactinide elements
- Acronym
- Actinides 2017
- Dates
- 9-14 Jul 2017
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 50023737
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; FISSION; FUEL PARTICLES; GRAPHITE; HIGH-LEVEL RADIOACTIVE WASTES; HTGR TYPE REACTORS; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; PLUTONIUM 240; SELF-SHIELDING; TRANSURANIUM ELEMENTS
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; CARBON; ELEMENTS; ENERGY SOURCES; EVEN-EVEN NUCLEI; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAVY NUCLEI; ISOTOPES; MATERIALS; MINERALS; NEUTRAL-PARTICLE TRANSPORT; NONMETALS; NUCLEAR REACTIONS; NUCLEI; PLUTONIUM ISOTOPES; RADIATION FLUX; RADIATION TRANSPORT; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; SIMULATION; SPONTANEOUS FISSION RADIOISOTOPES; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 10 refs., 5 figs., 2 tabs.