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R.J. Shields
R.J. Shields
Computer Sciences Corporation
Engineering
reactor safety
Neutron transport
Nuclear engineering
Coolant
3
Papers
3
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MELT3. Fast Reactor Transient Overpower Study
1986
A.E. Waltar
W.L. Partain
D.C. Kolesar
L.D. O'Dell
A. Padilla
J.C. Sonnichsen
N. P. Wilburn
H.J. Willenberg
R.J. Shields
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Effects of fuel density gradients and molten fuel freezing during a fast reactor excursion
1973
Transactions of the American Nuclear Society
W.L. Partain
A.E. Waltar
R.J. Shields
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MELT-II: A TWO-DIMENSIONAL NEUTRONICS-HEAT TRANSFER PROGRAM FOR FAST REACTOR SAFETY ANALYSIS.
1972
A.E. Waltar
A. Padilla
R.J. Shields
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