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  1. Kirk Truax

    BWR Fuel Assembly Question -- Why do BWRs have shrouds?

    Hey all, I was wondering if anyone could help me with a basic BWR question. Why do BWRs have shrouds? From what I've been able to find, this is a for "uniform cooling" but that's about it. My guess is that there are some thermal hydraulic benefits around maintaining nucleate boiling. Is...
  2. Kirk Truax

    PWR Refueling Systems and Procedures

    Thanks Jim! That's exactly the kinda resource I am looking for. Thank you for sharing. I agree, a co-op would defiantly be useful for this regard. Kirk
  3. Kirk Truax

    PWR Refueling Systems and Procedures

    Hey all, I was wondering if anyone can help me out with understanding the PWR refueling process? I'm an undergrad getting introduced to these systems and was hoping there was someone in the industry that might have some insight into the details of this. In regard to the removal of the old...
  4. Kirk Truax

    MCNP Geometry Error Tips

    Hey all, I was wondering if anyone had any good tips on debugging mcnp geometry? I'm an intermediate user working on better understanding the program. Does anyone have any tips or tricks that go beyond simply reading the manual?
  5. Kirk Truax

    MCNP : spatial position of interactions

    Hey there, I'm looking into a similar function of MCNP and I think you want to look into a data card called "PTRAC". This will output an additional file with the location of the interaction. I think this can also produce vector information that could potentially be useful for a hand computation...
  6. Kirk Truax

    How to find the best MCNP manuals?

    Hey there, I'm not sure if you are still having problems with this, but I might have a bit of insight here. MCNP6 is a combination of the functionality 5 and x. I don't have the exact definition of what makes those unique off the top of my head though. The best place to get info on how to...
  7. Kirk Truax

    Neutron fission cross section

    Hey guys, You were right, I definitely did leave out that vital bit of information. I was simply looking for the macroscopic cross section for thermal neutrons. I was modeling a sub-critical pile with a large amount of graphite moderation. Turns out I was able to find a ν∑f for UO2 to...
  8. Kirk Truax

    Neutron fission cross section

    Hey all, Does anyone happen to know the value of ν∑f for natural uranium? Here ν is the average number of neutron released from fission and ∑f is the macroscopic fission cross section of uranium. Kirk
  9. Kirk Truax

    How to simulate a D-D neutron generator with MCNP6?

    Hello Hector, I'm curious if you have found a solution to this problem since it has been posted. I am personally working on a D-T generator project at Oregon State and am about to run into the problem of distribution. Kirk