Recent content by werling3
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MCNP5 vs MCNP6.2 syntax difference
So I am getting a fatal error on a tally that contains a universe definition in it. f12:n (10<(u=1)) sd12 1.0 e12 0.1 20.0 the error specifically says "fatal error. invalid universe format in f card bin 1 tally 2." However, this input is able to run on MCNP5 without experiencing...- werling3
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- Difference Mcnp5
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- Forum: Nuclear Engineering