Approach to testing fusion components in existing nuclear facilities Page: 3 of 7
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The neutron energy distribution in a typical blanket module outer wall
has been calculated (Figure 1) and, with the exception of the 14 MeV spike,
the ETR fission spectrum is rowarkably close to the fusion spectrum
expected. The hulk heating from the ETR nuclear environment can be nuc'
hi nher than the anticipated heating of several typical bi nket concepts.
Although the shape of the ETR bulk heating curve iA different from the
others2-5 shown in Fiquro 2', it can be modii led uc:kj I.. shields,
react r pomer, lithium-6 nKl tini, -K.. tW Vi. ai ra p %O it ativa
configaration and level.
Surface heat and particle loads are pr, vi _. ,yer :f Ite
undergoing (n,p) reactions with incident th ernal neutrons. Estimates are
that up to 150 kW/m2 thermal load and up to 25 0W/42 fast particle load
:an he obtained at the surfac- of a ilankoc module eosed to the 31e.
Even greater fast particle heat fluxes can be obtaiand for materials
evaluatirns at the outer boundry of the 3He layer. This loading comes in
the form of protons and tritons striking the surfne at energies
representati ve of fusion plasma particles.
Fusion radiation damage to materials is often described by the r tio
of trapped He (appm, usually from n,atreactions) to atomic displacement per
.,ti: (dpa) brought aheut chiefly by neutron collisions. The He/dpa ratio
anticipated in fusion :ppl icatiens is typically orders of magnitude greater
tian thiat produced in f iion spectrum for non-niai c mot oria To
.irw ne this par;.meter n7 wil, it is sosrv that tri tinw produced in
e Hc i,; t w'i l re'd i y pr eiate most materials cins idt _' for Fy/2/',
1!icAtions.7'' Syie CF t h , wil decay intO 3H. Uidb (3cked
i(, the structure. Thm2 of W lOcked -Ye - .i. ii turn be convert d
lark to tritium by tho neutron flux. Hence, by pr nperly contra 'ing the
tritium concontra?.inn in the lie heating layer FWr the material and
ratrrn flux employed, it a paar; possible to simula& the b.dh ratio and
this get a reason ibe citate of .material respn a f us ion (inviron-
mernts. Experiment3i dat a from other fac ilities such as -TN I1 and FiMIIT
oil st ill be reni red to henchmark resul Ls.
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Hsu, P.Y.; Miller, L.G.; Longhurst, G.R.; Masson, L.S. & Kulcinski, G.L. Approach to testing fusion components in existing nuclear facilities, article, January 1, 1980; United States. (https://digital.library.unt.edu/ark:/67531/metadc1058455/m1/3/: accessed April 18, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.