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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
C. Petitjean, F. Atchison, G. Heidenreich, H. K. Walter, F. Amelotti, R. Andreani, F. de Marco, S. Monti, M. Pillon, M. Vecchi, V. E. Markushin, L. I. Ponomarev, C. Niebuhr
Fusion Science and Technology | Volume 25 | Number 4 | July 1994 | Pages 437-450
Technical Paper | Fusion Reactor | doi.org/10.13182/FST94-A30251
Articles are hosted by Taylor and Francis Online.
A design study is presented for an intense 14-MeV neutron source based on muon-catalyzed fusion to be used for first-wall and blanket material research for future fusion reactors. Negative pions are produced inside a 5- to 10-T magnetic field by an intense deuteron beam interacting with a 30- to 50-cm-long carbon target. The pions and the muons resulting from the decay of pions inflight are collected in the backward direction and stopped in a high-density deuterium-tritium (D-T) target. With an 18-MWdeuteron beam at 1.5 GeV (12 mA = 7.5 × 1016 d/s), ∼ 1016 π−/s can be generated, which will decay to muons of which up to 1015 μ−/s stop in the D-T mixture. Assuming Xc = 100 fusions per muon, muon-catalyzed fusion produces 14-MeV neutrons with a source strength of up to 1017 n/s, i.e., a neutron power of 200 kW. A neutron flux of up to 1014/cm2·s (10 dpa/yr) can be achieved in test volumes of several litres. These numbers, however, do not represent a technological limit. This source has about the same power efficiency for neutron generation as low-energy beams (d-Li stripping). It also has the advantage of producing the original 14-MeV fusion spectrum without tails, isotropically into a 4π solid angle. In addition, the power density and heat load of the primary target are a considerably smaller problem. The environment of the secondary target, the neutron source itself, can be made to resemble part of the tokamak ring to be simulated. The noninteracting part of the beam (30 to 40%) can be disposed of separately or reused for another facility (e.g., a spallation neutron source).