Fuel particle balance study in FFHR DEMO reactor
- 1. National Institute for Fusion Science, Toki, Gifu (Japan)
Description
Tritium particle balance in the FFHR DEMO reactor is investigated with consideration of the fueling efficiency by pellet injection system, retention loss in a vacuum vessel and permeation loss from the fuel processing system. In order to satisfy the fuel balance and the tritium safety management, it was necessary to suppress the tritium retention rate to be 10-5 and the DFs in the tritium cycle systems to above 107 with the tritium breeding ratio of 1.08. The processing throughput for the tritium processing system is estimated to be about 400 mol/h, which is almost same as the throughput of the fuel stream for the ITER. Therefore, the tritium processing system for vacuum exhaust gas for the DEMO will not be necessary to improve the system for the ITER further. On the other hands, the significant development of the tritium processing system for the effluent disposal and the waste materials from the safety aspect and the social acceptance will be required toward the DEMO reactor. (author)
Availability note (English)
Available from http://dx.doi.org/10.1585/pfr.7.2405023Additional details
Identifiers
Publishing Information
- Journal Title
- Plasma and Fusion Research
- Journal Volume
- 7
- Journal Issue
- special issue 1
- Journal Page Range
- p. 2405023.1-2405023.4
- ISSN
- 1880-6821
Conference
- Title
- 21. international Toki conference on integration of fusion science and technology for steady state operation
- Acronym
- ITC21
- Dates
- 28 Nov - 1 Dec 2011
- Place
- Toki, Gifu (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 46134541
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; D-T OPERATION; D-T REACTORS; LHD DEVICE; MASS BALANCE; NUMERICAL SOLUTION; THERMONUCLEAR FUELS; THERMONUCLEAR REACTOR FUELING; TRITIUM; TRITIUM EXTRACTION PLANTS; TRITIUM RECOVERY
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; FUELS; HYDROGEN ISOTOPES; INDUSTRIAL PLANTS; ISOTOPE SEPARATION PLANTS; ISOTOPES; LIGHT NUCLEI; MATHEMATICAL SOLUTIONS; NUCLEAR FACILITIES; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 18 refs., 6 figs.