Published October 2007 | Version v1
Journal article

Estimation and control of beryllium-7 behavior in liquid lithium loop of IFMIF

  • 1. Japan Atomic Energy Agency, 2-4 Shirakata, Tokai, Ibaraki 319-1195 (Japan)

Description

In the IFMIF liquid lithium target system, beryllium-7 (7Be) produced by deuteron-lithium (D-Li) reaction is the dominant radioactive nuclide at maintenance of the lithium loop components, since the dose equivalent rate of the 7Be is several orders of magnitude larger than that due to other nuclides. Behavior of 7Be, such as solubility and deposition in the liquid lithium was estimated considering temperature gradient in the loop. The result showed that all most all 7Be, 5.02 x 1015 Bq, would be deposited on most downstream part of the heat exchanger with the lowest temperature among the main flow. Subsequent estimation for dose equivalent rate due to this localized radioactive source showed that, without radiation shielding, the rate would be 8.5 x 107 μSv/h, about seven orders of magnitude higher than a guideline of 10 μSv/h for yearly working time of 2000 h. Required thickness of radiation shield made of lead was found to be 8 cm

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2007.07.014

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2007.07.014;
PII
S0920-3796(07)00356-0;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
82
Journal Issue
15-24
Journal Page Range
p. 2490-2496
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
24. symposium on fusion technology
Acronym
SOFT-24
Dates
11-15 Sep 2006
Place
Warsaw (Poland)

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.