Chernobyl Nuclear Accident Congressional Hearings Transcript

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of the reactor core melted. Unlike, however, the Chernobyl incident,
the amount of fission products released from the TMI-2 reactor
to the environment posed no significant threat to the public.
The scenario for the progression of the TMI accident would indicate
that the relocation of the core into a reactor lower plenum
that remains full of water will probably result in coolable debris
which will arrest the accident. The reactor primary vessel integrity
was maintained there. We believe it would be maintained in a similar
accident, and as I mentioned, that information from TMI correlated
very well with the experimental work done on the reactors
LOFT and PBF.
Each of the facilities and test programs have contributed to the
safety and to the information base from which the adequacy of
commercial reactor designs and their safety and regulatory criteria
are confirmed.
Many of the reactor codes that the Nuclear Regulatory Commission
uses for licensing commercial power reactors are based on experimental
data and analysis done by the Department of Energy.
The eventual impact of Chernobyl on existing light water reactors
is difficult to assess. I believe that as was the case with TMI-2,
as more information is available from the Chernobyl accident, we
will begin to refocus the U.S. program. I do not see significant refocusing.
I believe that we will continue the work on the program,
such as severe accident phenomena, particularly as it might relate
to containment response; we will continue to work on the resolution
of the fission product release and source-term issue; and we
will continue to minimize the human factor in reactor operations
and control room designs.
I believe the Chernobyl accident will ultimately confirm the
quality of U.S. safety technology. I am confident that the vast experience
and expertise available at the DOE National Laboratories
will contribute to the understanding and resolution of concerns
raised by the accident at the Chernobyl plant.
We are continuing to work on advanced reactor safety at the
INEL. We recently did a test on the liquid metal reactor called
EBR-2 in which a loss of coolant, without reactor scram, provided
for the automatic shutdown of the reactor. We continue to work
with the Gas-Cool Reactor Association on their inherently safe designs.
I therefore see that many of these inherently safe reactor designs
will receive a high priority. It is imperative that the safety of these
next generation reactors be supported by tests and we have a program
to do that.
Internationally, I believe it is important that the United States
continue its
involvement in IAEA and other international efforts
so that we may fully understand the effects of the Chernobyl accident
and that can indeed be inputed into the U.S. designs and research
and development.
That concludes my summary, Mr. Chairman. Thank you for the
opportunity.
[The prepared statement of Mr. Wade follows:]