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Title: A vacuum disengager for tritium removal from HYLIFE-II Reactor Flibe

Conference ·
OSTI ID:10172678
;  [1];  [2]
  1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
  2. Missouri Univ., Columbia, MO (United States). Dept. of Nuclear Engineering

We have designed a vacuum disengager system to remove tritium from the Flibe (Li{sub 2}BeF{sub 4}) molten salt coolant of the HYLIFE-II fusion reactor. There is a two-stage vacuum disengager in each of three intermediate heat exchanger (IHX) loops. Each stage consists of a vacuum chamber 4 m in diameter and 7 m tall. As 0.2 mm diameter molten salt droplets fall vertically downward into the vacuum, most of the tritium diffuses out of the droplets and is pumped away. A fraction {Phi} {approximately}10{sup {minus}5} of the 8.6 MCi/day tritium source (from breeding in the Flibe and from unburned fuel) remains in the Flibe as it leaves the vacuum disengagers, and about 21% of that permeates into the intermediate coolant loop, so about 20 Ci/day leak into the steam system. With Flibe primary coolant and a vacuum disengager, it appears that an intermediate coolant loop is not needed to prevent tritium from leaking into the steam system. An experiment is needed to demonstrate Flibe vacuum disengager operation.

Research Organization:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
10172678
Report Number(s):
EGG-M-91508; CONF-920607-18; ON: DE92017886
Resource Relation:
Conference: 10. topical meeting on technology of fusion energy,Boston, MA (United States),7-12 Jun 1992; Other Information: PBD: [1992]
Country of Publication:
United States
Language:
English