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A Novel Approach to Fabricating Fuel Compacts for the Next Generation Nuclear Plant (NGNP)

Journal Article · · Journal of Nuclear Materials

The next generation nuclear plant (NGNP) is a combined complex of a very high temperature reactor (VHTR) and hydrogen production facility. The VHTR can have a prismatic or pebble bed design and is powered by TRISO fuel in the form of a fuel compact (prismatic) or pebble (pebble bed). The US is scheduled to build a demonstration VHTR at the Idaho National Laboratory site by 2020. The first step toward building of this facility is development and qualification of the fuel for the reactor. This paper summarizes the research and development efforts performed at Oak Ridge National Laboratory (ORNL) toward development of a qualified fuel compact for a VHTR.

Research Organization:
Oak Ridge National Laboratory (ORNL)
Sponsoring Organization:
NE USDOE - Office of Nuclear Energy
DOE Contract Number:
AC05-00OR22725
OSTI ID:
941027
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1-2 Vol. 381; ISSN 0022-3115; ISSN JNUMAM
Country of Publication:
United States
Language:
English

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