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Title: Concept of DT fuel cycle for a fusion neutron source

A concept of DT-fusion neutron source (FNS) with the neutron yield higher than 10{sup 18} neutrons per second is under design in Russia. Such a FNS is of interest for many applications: 1) basic and applied research (neutron scattering, etc); 2) testing the structural materials for fusion reactors; 3) control of sub-critical nuclear systems and 4) nuclear waste processing (including transmutation of minor actinides). This paper describes the fuel cycle concept of a compact fusion neutron source based on a small spherical tokamak (FNS-ST) with a MW range of DT fusion power and considers the key physics issues of this device. The major and minor radii are ∼0.5 and ∼0.3 m, magnetic field ∼1.5 T, heating power less than 15 MW and plasma current 1-2 MA. The system provides the fuel mixture with equal fractions of D and T (D:T = 1:1) for all FNS technology systems. (authors)
Authors:
; ; ;  [1] ; ;  [2]
  1. NRC Kurchatov Institute, Moscow (Russian Federation)
  2. FSUE RFNC - VNIIEF, Sarov (Russian Federation)
Publication Date:
OSTI Identifier:
22429688
Resource Type:
Journal Article
Resource Relation:
Journal Name: Fusion Science and Technology; Journal Volume: 67; Journal Issue: 2; Conference: TRITIUM 2013: 10. International Conference on Tritium Science and Technology, Nice Acropolis (France), 21-25 Oct 2013; Other Information: Country of input: France; 3 refs.
Country of Publication:
United States
Language:
English
Subject:
07 ISOTOPES AND RADIATION SOURCES; ACTINIDES; D-T OPERATION; FUEL CYCLE; NEUTRON DIFFRACTION; NEUTRON SOURCES; NEUTRONS; RADIOACTIVE WASTE PROCESSING; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TRANSMUTATION