Back to Search Start Over

Study of a spherical torus based volumetric neutron source for nuclear technology testing and development

Authors :
R.J Cerbone
Edward T. Cheng
Yueng Kay Martin Peng
L.D Galambos
I.N. Sviatoslavsky
Source :
Fusion Engineering and Design. 48:299-306
Publication Year :
2000
Publisher :
Elsevier BV, 2000.

Abstract

A plasma based, deuterium and tritium (DT) fueled, volumetric 14 MeV neutron source (VNS) has been considered as a possible facility to support the development of the demonstration fusion power reactor (DEMO). It can be used to test and develop necessary fusion blanket and divertor components and provide sufficient database, particularly on the reliability of nuclear components necessary for DEMO. The VNS device can be complement to ITER by reducing the cost and risk in the development of DEMO. A low cost, scientifically attractive, and technologically feasible volumetric neutron source based on the spherical torus (ST) concept has been conceived. The ST-VNS, which has a major radius of 1.07 m, aspect ratio 1.4, and plasma elongation three, can produce a neutron wall loading from 0.5 to 5 MW m−2 at the outboard test section with a modest fusion power level from 38 to 380 MW. It can be used to test necessary nuclear technologies for fusion power reactor and develop fusion core components include divertor, first wall, and power blanket. Using staged operation leading to high neutron wall loading and optimistic availability, a neutron fluence of more than 30 MW year m−2 is obtainable within 20 years of operation. This will permit the assessments of lifetime and reliability of promising fusion core components in a reactor relevant environment. A full scale demonstration of power reactor fusion core components is also made possible because of the high neutron wall loading capability. Tritium breeding in such a full scale demonstration can be very useful to ensure the self-sufficiency of fuel cycle for a candidate power blanket concept.

Details

ISSN :
09203796
Volume :
48
Database :
OpenAIRE
Journal :
Fusion Engineering and Design
Accession number :
edsair.doi...........1858eece5a31f5d8713d9755442aa137
Full Text :
https://doi.org/10.1016/s0920-3796(00)00165-4