Published December 1989 | Version v1
Report Restricted

Neutronics studies for the ARIES-I reactor

Description

A high-performance helium-cooled, solid breeder fusion blanket was designed for the innovative ARIES-I reactor. The Li4SiO4 breeder material is placed behind a beryllium zone to maximize the beryllium neutron multiplication. A modest beryllium inventory of about 40 metric tons is needed to achieve a blanket energy multiplication of 1.35 or more, while breeding adequate tritium in the blanket. The decay heat values and radiological hazard potentials of ARIES-I blanket and shield (SiC + B4C) materials are found to be at least two to three orders of magnitude lower than those from metallic alloys such as ferritic steel and vanadium alloy. Inherent safety will be achieved for the ARIES-I blanket because the minimum radioactive inventory precludes meltdown of the first wall and structural SiC material. However, the safety design of the divertor which uses tungsten alloy particle-collector plates and vanadium alloy structure will need to be carefully done because of higher levels of afterheat. All ARIES-I components will qualify for disposal as 10 CFR 61 Class C waste if averaging over the first wall and blanket component is allowed, and if some exotic impurity elements (Ag, Nb, Mo) are controlled below 1 ppM. 10 refs., 3 figs., 5 tabs

Availability note (English)

MF available from INIS under the Report Number; NTIS, PC A02/MF A01 as DE90004095; OSTI; INIS; US Govt. Printing Office Dep.

Files

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Additional details

Publishing Information

Imprint Pagination
4 p.
Report number
GA-A--19765

Conference

Title
13. IEEE symposium on fusion engineering.
Dates
2-6 Oct 1989.
Place
Knoxville, TN (USA).

Optional Information

Contract/Grant/Project number
Contract AC03-89ER52153
Secondary number(s)
CONF-891007--114.