Nuclear Analysis of a Tokamak Experimental Power Reactor Conceptual Design
- 1 August 1977
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 35 (1) , 51-79
- https://doi.org/10.13182/nt77-a31850
Abstract
Detailed nuclear analysis of a reference conceptual design for a tokamak experimental power reactor (EPR) is presented. The reference EPR has a 6.25-m major radius and a 2.1-m minor radius circular plasma with a nominal neutron wall loading of 0.5 MW/m2. A 0.28-m-thick blanket of stainless steel surrounds a stainless-steel vacuum vessel. The inner shield consists of stainless steel and B4C and is 0.58 m thick. The 0.97-m-thick outer shield employs lead mortar, stainless steel, and graphite. The neutronics results in the first wall and blanket vary significantly in the poloidal direction due to an outward shift in the deuterium-tritium neutron source distribution and the toroidal curvature. The infinite cylinder approximation overestimates response rates in the first wall compared with toroidal geometry calculations. Neutral beam lines, vacuum ducts, and other penetrations of the blanket and bulk shield represent large (∼0.6- to 1.0-m2 cross section) streaming paths for neutrons and require special shieldi...Keywords
This publication has 4 references indexed in Scilit:
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