Oak Ridge National Laboratory Institutional Plan: FY 1982-1987
Oak Ridge National Laboratory Institutional Plan: FY 1982-1987
Oak Ridge National Laboratory Institutional Plan: FY 1982-1987
Create successful ePaper yourself
Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.
16 <strong>Oak</strong> <strong>Ridge</strong> <strong>National</strong> <strong>Laboratory</strong> <strong>Institutional</strong> <strong>Plan</strong> <strong>FY</strong> <strong>1982</strong>-<strong>FY</strong> <strong>1987</strong><br />
tokamak stability in collaboration with the Impurity<br />
Study Experiment (ISX-B) program. In the EBT<br />
area, the efforts to model confinement will continue,<br />
and, in particular, the effects of high-core plasma<br />
beta will be studied. Efforts are increasing in the<br />
area of advanced toroidal concepts; emphasis is on<br />
the effects of externally applied helical fields.<br />
Work continues in an applied plasma physics effort<br />
to develop advanced laser diagnostics. For example, a<br />
multichord Faraday rotation system that measures the<br />
plasma current profile on ISX-B has been developed<br />
and should begin providing data in <strong>FY</strong> <strong>1982</strong>.<br />
Activities pertaining to atomic physics data will<br />
continue analyzing and disseminating important data<br />
for the fusion community and, where needed, will<br />
measure cross sections of multicharged ions.<br />
Tokamak Systems (AT 10 10). The ISX-B<br />
device continues to produce critical information for<br />
the tokamak program. High-beta studies of circular<br />
and noncircular plasmas continue, as well as parallel<br />
programs in pellet fueling, impurity studies, electron<br />
cyclotron heating, magnetic ripple effects, and diag<br />
nostic development. In <strong>FY</strong> <strong>1982</strong> a bundle divertor<br />
and improved diagnostics will be installed. We<br />
expect the ISX-B program to continue into 1984.<br />
As a result of broadened interest shown by other<br />
laboratories and DOE in improving the tokamak con<br />
cept, the ISX-C program and device are being<br />
modified and renamed ATF to emphasize the study of<br />
improved toroidal confinement features. Included will<br />
be studies of the effects of helical coils on stability<br />
and confinement and of the principles of steady-state<br />
operation. The ATF operation should start in 1985.<br />
Development and Technology (AT 15). The<br />
major development activities in this area are super<br />
conducting magnets and neutral beams. The delivery<br />
of the first three coils for the Large Coil Program<br />
(two from the United States and one from Japan) is<br />
expected in mid <strong>FY</strong> <strong>1982</strong>, and testing should begin<br />
early in <strong>FY</strong> 1983. The remaining U.S. coil and the<br />
two other international coils (from Euratom and<br />
Switzerland) should be delivered in <strong>FY</strong> 1983 and<br />
should lead to full-scale tests in <strong>FY</strong> 1984. Develop<br />
ment work on high-field conductor and magnet<br />
designs suitable for high-field tokamak magnets will<br />
continue.<br />
The Poloidal Divertor Experiment (PDX)/ISX-B<br />
neutral-beam development activity has been com<br />
pletely successful. Develop ment in the area of long-<br />
pulse beams, in support of the MFTF-B device at<br />
Lawrence Livermore Natonal <strong>Laboratory</strong> and ATF,<br />
has begun and will contii ae through 1984. Efforts<br />
in the areas of radiofrequency heating technology and<br />
negative ion-based neutral beams are expected to<br />
increase. In addition, significant work is in progress<br />
on (1) developing materials for fusion reactors, (2)<br />
developing accelerators that use solid hydrogen pellets<br />
to fuel plasma devices, (3) characterizing the plasma-<br />
wall interaction, and (4) developing techniques for<br />
calculating neutron transport in complex geometries<br />
and for checking the calculations against experimental<br />
results.<br />
The Fusion Engineering Design Center (FEDC) has<br />
completed a preliminary design of the Fusion<br />
Engineering Device (FED) and is preparing to colla<br />
borate in expanded studies during <strong>FY</strong> <strong>1982</strong> and<br />
1983. The FEDC's future role is being discussed.<br />
Design studies of the FED and of the tokamak and<br />
EBT demonstration reactors serve as a focus for the<br />
plasma physics experiments and for technology<br />
development.<br />
Finally, a first draft of a generic environmental<br />
impact statement for magnetic fusion power systems<br />
has been prepared and will continue to be refined.<br />
Biomedical and Environmental<br />
Research (HA 02)<br />
This activity encompasses a broad effort to under<br />
stand the interaction of energy-related pollutants with<br />
living organisms, including their transport, chemical<br />
evolution, and ultimate fate in the environment. The<br />
similarity of the environmental processes controlling<br />
the fates of many different pollutants makes a broad<br />
approach especially productive. Sedimentation and<br />
sediment transport are studied to define the principal<br />
reservoirs and vectors of pollutants; this information<br />
is being used in ongoing DOE activities to ensure that<br />
they are conducted safely and effectively and that<br />
potential hazards to humans and ecological systems<br />
can be identified, evaluated, and anticipated. One