Community Research and Development Information Service - CORDIS

Abstract

Fusion reactor designs specify among others Li17Pb83 alloys as breeder material candidate with water as coolant. From the safety standpoint water leakage in the blanket cannot be excluded. The interaction of the alloy with water or steam could therefore be a safety concern for the integrity of the blanket housing. In order to gain knowledge on the safety limits studies have been performed on reaction kinetics of Li17Pb83 with steam, measurement of the mechanical work release from Li17Pb83/water interactions, and calculation of the loading and response of blanket housings due to Li17Pb83/water interactions.

Additional information

Authors: KOTTOWSKI H M, JRC Ispra Estab. (IT);RENDA V, JRC Ispra Estab. (IT);KUHLBOERSCH G, JRC Ispra Estab. (IT)
Bibliographic Reference: Paper presented: ENC 4: Fourth International ENS/ANS Conference, Geneve (CH), June 1-6 1986
Availability: Available from (1) as Paper EN 32692 ORA
Record Number: 198910396 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en