On February 27, 1986, Acting Assistant Secretary for Nuclear
Energy, James W. Vaughan, Jr., appeared before the Science
and Technology Subcommittee on Energy Research and Produc-
tion, to discuss the authorization for nuclear fission
research and development and nuclear fission programs.
Mr. Vaughan was accompanied by Delbert F. Bunch, Acting
Deputy Assistant Secretary for Reactor Development and Jerry
Griffith, Acting Associate Deputy Assistant Secretary for
Reactor Systems Development and Technology.

Following that hearing, you submitted written questions for
Enclosed are the
our response to supplement the record.

answers to those questions, which also have been sent
directly to the Committee staff.

If you have any questions, please have your staff call Mike
Gilmore or Cathy Hamilton on 252-4277.

They will be happy

Al Abben

Robert G. Rabben

Assistant General Counsel
for Legislation

(375)

POST-HEARING QUESTIONS AND ANSWERS

RELATING TO THE

FEBRUARY 27, 1986 HEARING

BEFORE THE

HOUSE COMMITTEE ON SCIENCE AND TECHNOLOGY

SUBCOMMITTEE ON ENERGY RESEARCH AND PRODUCTION

WITNESS: JAMES W. VAUGHAN, JR.

ACTING ASSISTANT SECRETARY FOR NUCLEAR ENERGY

U.S. DEPARTMENT OF ENERGY

QUESTIONS FROM CHAIRMAN MARILYN LLOYD

High Temperature Gas Reactor (HTGR)

Question 1:

How can the Department of Energy substantiate a position that fails to recognize that it takes 10 to 15 years to develop a new reactor and that, if the Department fails to fulfill its research and development mission to develop safer reactors for the future, which it seems bound to do, the public will still not accept the nuclear option in the mid 1990's when current projects indicate a need for more new plant starts?

Answer:

The Department recognizes that it takes 10 to 15 years to
develop a new reactor. The central focus of the Department's
civilian research and development (R&D) effort is and shall
continue to be the development of an economic, inherently
safe advanced reactor system that is acceptable to the public
and the market place. The process by which the Department is
conducting this development activity is an iterative one
between user requirements, technological understanding,
conceptual design and economic analysis. Substantial
progress in the advanced converter program has been made to
the point that key technological and regulatory development
requirements have been identified and the program is focused
on meeting these requirements. Cost-sharing will be pursued

as one means to complete detailed designs and subsequently
deploy advanced converters.

-2

Answer 1
(continued):

The advanced civilian reactor development program has embarked on a course destined to develop advanced nuclear systems that meet market demands. Our rate of progress on that course must be tempered by fiscal constraint. However, we have made important progress and our resolve to meet our objectives is undiminished.

QUESTIONS FROM CHAIRMAN MARILYN LLOYD

High Temperature Gas Reactor (HTGR) and Fuel Cycle Program
Question 2:

What work is Oak Ridge doing on the modular HTGR program in
FY 1986 and what is the extent of the funding for this
effort?

Answer:

The work underway in FY 1986 at the Oak Ridge National
Laboratory (ORNL) in support of the modular HTGR is focussed
primarily on technology development, with the major efforts
being the developing and testing of reference coated particle
fuel, irradiation resistant graphites, and high temperature
alloys. The fuel development and testing efforts include an
irradiation testing program that involves capsule
fabrication, test monitoring, and post-irradiation hot cell
examination.

Also, this effort includes out-of-pile testing

of irradiated fuel to quantify fission product retention
under accident conditions.

The graphite development work is concentrated on providing a
better understanding of the fracture mechanics and behavior
of the reference fuel element and core support graphites; the
alloy testing program involves continuing efforts to provide
the large data base required for the steam generator, hot
duct, and thermal barrier alloys.