Published 1988 | Version v1
Journal article

Trench reactor: an overview

Description

Recent fast, sodium-cooled reactor designs reflect new conditions. In nuclear energy these conditions are (a) emphasis on maintainability and operability, (b) design for more transparent safety, and (c) a surplus of uranium and enrichment availability that eases concerns about light water reactor fueling costs. In utility practice the demand is for less capital exposure, short construction time, smaller new unit sizes, and low capital cost. The PRISM, SAFR, and integral fast reactor (IFR) concepts are responses to these conditions. Fast reactors will not soon be deployed commercially, so more radical designs can be considered. The trench reactor is the product of such thinking. Its concepts are intended as contributions to the literature, which may be picked up by one of the existing programs or used in a new experimental project. The trench reactor is a thin-slab, pool-type reactor operated at very low power density and- for sodium-modest temperature. The thin slab is repeated in the sodium tank and the reactor core. The low power density permits a longer than conventional core height and a large-diameter fuel pin. Control is by borated steel slabs that can be lowered between the core and lateral sodium reflector. Shutdown is by semaphore slabs that can be swung into place just outside the control slabs. The paper presents major characteristics of the trench reactor that have been changed since the last report

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
57
Series
Trans. Am. Nucl. Soc.
Journal Page Range
316-317
ISSN
0003-018X
CODEN
TANSA

Conference

Title
Joint meeting of the European Nuclear Society and the American Nuclear Society.
Dates
30 Oct - 4 Nov 1988.
Place
Washington, DC (USA).

Optional Information

Secondary number(s)
CONF-881011--.