Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) (NUREG/CR-6944) - Volume 5: Graphite PIRTs
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Manuscript Completed: October 2007
Date Published: March 2008
T.D. Burchell – Panel Chair
R. Bratton (INL)
B. Marsden (University of Manchester))
Oak Ridge National Laboratory
P.O. Box 2008
Oak Ridge, TN 37831-6170
S. Basu, NRC Project ManagerNRC Job Code N6376
Office of Nuclear Regulatory Research
Here we report the outcome of the application of the Nuclear Regulatory Commission (NRC)
Phenomena Identification and Ranking Table (PIRT) process to the issue of nuclear-grade graphite for the
moderator and structural components of a next generation nuclear plant (NGNP), considering both routine
(normal operation) and postulated accident conditions for the NGNP. The NGNP is assumed to be a
modular high-temperature gas-cooled reactor (HTGR), either a gas-turbine modular helium reactor (GT-MHR)
version [a prismatic-core modular reactor (PMR)] or a pebble-bed modular reactor (PBMR)
version [a pebble bed reactor (PBR)] design, with either a direct- or indirect-cycle gas turbine (Brayton
cycle) system for electric power production, and an indirect-cycle component for hydrogen production. NGNP design options with a high-pressure steam generator (Rankine cycle) in the primary loop are not considered in this PIRT. This graphite PIRT was conducted in parallel with four other NRC PIRT activities, taking advantage of the relationships and overlaps in subject matter.
The graphite PIRT panel identified numerous phenomena, five of which were ranked high importance–low knowledge. A further nine were ranked with high importance and medium knowledge rank. Two phenomena were ranked with medium importance and low knowledge, and a further 14 were ranked medium importance and medium knowledge rank. The last 12 phenomena were ranked with low importance and high knowledge rank (or similar combinations suggesting they have low priority). The ranking/scoring rationale for the reported graphite phenomena is discussed.
Much has been learned about the behavior of graphite in reactor environments in the 60-plus years
since the first graphite rectors went into service. The extensive list of references in the Bibliography is
plainly testament to this fact. Our current knowledge base is well developed. Although data are lacking
for the specific grades being considered for Generation IV (Gen IV) concepts, such as the NGNP, it is
fully expected that the behavior of these graphites will conform to the recognized trends for near isotropic
nuclear graphite. Thus, much of the data needed is confirmatory in nature. Theories that can explain
graphite behavior have been postulated and, in many cases, shown to represent experimental data well.
However, these theories need to be tested against data for the new graphites and extended to higher
neutron doses and temperatures pertinent to the new Gen IV reactor concepts. It is anticipated that
current and planned future graphite irradiation experiments will provide the data needed to validate many of the currently accepted models, as well as providing the needed data for design confirmation.