STAR: The Secure Tranportable Autonomous Reactor system, Encapsulated Fission Heat Source. Progress report for period terminating March 31, 2000 Page: 4 of 54
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Task 1
Several layouts of the ENHS have been developed. These include a novel layout that uses a
cover-gas lift-pump for helping the circulation of the primary coolant. Our analysis indicates that
it should be possible to manufacture and fuel the ENHS in the factory, and ship it complete and
sealed to the site.
Task 2
Our analysis so far indicates that 4 mm is an adequate thickness for the confinement wall, and
that with such a wall thickness it is possible to transfer the power from the primary to the
secondary coolant with a temperature drop not exceeding 50*C.
Task 3
Acceptable structural wall thickness for the ENHS was found to be 5 cm.
Task 4
It was found possible to design the ENHS primary coolant to have 100% natural circulation.
Several dozen alternative designs having 100% natural circulation along with 50"C primary-to-
secondary temperature drop were worked out. A one-dimensional simulation model has been
developed and is being applied to transient analysis of the primary coolant. It was found that it is
feasible to operate the ENHS with 100% natural circulation of the primary coolant over the
entire range from very low power level to full power.
Task 7
Different approaches to the design of decay heat removal systems have been evaluated. A
PRISM like RVACS system was adopted for the ENHS. If cover-gas lift-pump will be adopted
for the ENHS, the cover-gas system will be used as an additional decay heat removal system.
Scenarios to analyze for studying the feasibility of decay heat removal were defined. A transient
analysis simulation model for decay heat removal is being developed.
Task 9
Reactivity coefficients have been calculated for the reference core. Transient analysis simulation
model has been developed for the primary system. Preliminary analysis indicates that the ENHS
has a good load following capability.
Task 13
We have identified a scenario for the insertion of the ENHS module into the pool. The insertion
will be done with the fuel embedded in solidified lead or Pb-Bi. After insertion into the pool, the
Pb (or Pb-Bi) will be melted.
Task 18
No progress was made so far.
Task 19
A couple of novel approaches were conceived for the IHX design. They appear to be simpler to
implement than the corrugated confinement wall. One of the design approaches uses circular
tubes for the IHX while the other uses channels that are rectangular in cross section. Thermo-
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Greenspan, Ehud. STAR: The Secure Tranportable Autonomous Reactor system, Encapsulated Fission Heat Source. Progress report for period terminating March 31, 2000, report, April 24, 2000; Berkeley, California. (https://digital.library.unt.edu/ark:/67531/metadc720718/m1/4/: accessed April 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.