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Title:
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In-pile testing of HCPB submodules: feasibility study for the European Blanket Project: final report
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Author(s):
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Published by:
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Publication date:
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ECN
NUCLEAIR
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1998
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ECN report number:
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Document type:
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ECN-I--98-013
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Other
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Number of pages:
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Full text:
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43
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Download PDF
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Abstract:
Full size module systems of the candidate DEMO blanket concepts selectedfor the European Blanket Project (EBP) will be tested in ITER, presently
called Test Blanket modules (TBM). The Helium Cooled Pebble Bed (HCPB) is one
of the two concepts developed in the European Union (EU). This development
path consists of several scaling steps, including integral testing of a
subsized module at realistic operation conditions. As part of the HCPB
development work for the TBMs, ECN performed jointly with JRC/IAM at Petten
a feasibility study for irradiation tests of subsized HCPB modules. The first
stage of the study was concluded with a report on the conceptual design of an
in-pile test of a single submodule with a helium cooling loop. Such test was
considered technically feasible, but would require significant project
duration and expenditures. Further development of detailed objectives for
in-pile tests was recommended, in particular in view of the different
parameters for the HCPB-ITM and DEMO-concept. This objective has been
modified by the EBP in fall 1997. For the final stage of the study the test
objective has been: the in-pile testing of the thermal/mechanical behaviour
of the HCPB ceramic breeder beds, while giving lower priority to tritium
transport issues (release, permeation). Several configuration options in the
High Flux Reactor (HFR) in Petten, Netherlands, to perform in-pile test of
HCPB submodules have been considered. Neutronics analyses along with thermal
and structural analyses have been made for selected options and several HFR
peripheral in-tank positions. These pre-design analyses show that the whole
range of breeder bed power densities and temperature levels, which are
relevant to the HCPB DEMO and BTM designs, can be reached with the options
presented. The options are all cooled by the reactor coolant flow. The use of
an helium loop is not compulsory and is considered as an unnecessary
complication with regard to the present test objectives. Relevant lithium
burnups can be reached in a reasonable time scale, due to a high availability
of the HFR. The proposed type of irradiation experiment can be readily
detailed and realized. 21 refs.
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