Why Do MCNP5 Statistical Tests Fail Despite Increasing Particle Numbers?

In summary: variance...
  • #1
Van525
3
0
Can anyone tell me how I can solve the problem of non-verification of statistical tests done by MCNP5 (relative error, VOV, figure of Merite, slope). I tried to increase the number of particles generated in order to hope to verify the tests but it did not work.
 
Engineering news on Phys.org
  • #2
The way to get the statistics depends on the details of the problem. For example, the nature of problems involving heavy shielding has one set of methods. Problems involving kcode have a different set of methods.

So, if you can post your code, that might help. If you cannot (maybe there are proprietary or confidential items in it) then at least can you describe the general nature of your problem?
 
  • #3
Here can you find my output file. You can see for all my tally 5, the statistical tests are not completed for 100.000.000 particles.
 

Attachments

  • note.txt
    281.9 KB · Views: 82
  • #4
Sigh. A post that contained absolutely none of the description of your input, just quoted more detail about the stat tests that failed.

Nope. If you can't post your input, and you can't describe the basic nature of the problem, not going to help you.
 
  • Like
Likes Alex A
  • #5
The problem I have at the moment is the unacceptability of the basic statistical tests done by MCNP5.
The idea of my simulation is to place tally5 at different angles to the direction of emission of the primary X-ray beam. The tally I define are all of 1cm radius (in order to simulate a point detector (CZT)) and all placed at 2m from the source. It is logical to increase the number of particles as much as possible in order to hope to accept statistical tests (relative error function of the root number of particle history etc. ) but in my case some tests are not accepted by MC. Would you have any clues to solve this problem? Thank you very much

Here an example of the statistical test (VOV and PDF) of tally 85 who are not accepted.
===================================================================================================================================

results of 10 statistical checks for the estimated answer for the tally fluctuation chart (tfc) bin of tally 85

tfc bin --mean-- ---------relative error--------- ----variance of the variance---- --figure of merit-- -pdf-
behavior behavior value decrease decrease rate value decrease decrease rate value behavior slope

desired random <0.05 yes 1/sqrt(nps) <0.10 yes 1/nps constant random >3.00
observed random 0.00 yes yes 0.27 yes yes constant random 2.66
passed? yes yes yes yes no yes yes yes yes no

===================================================================================================================================
 
  • #6
If you are throwing 100'000'000 particles at a problem and your tallies are not statistically significant it's probably in the design. If your source is 2m from your detector and isotropic, and your detector is 1cm radius then only... ~ 2 * Pi / (4 * Pi * 2000^2) = 1/ 8'000'000 of the area is covered. So almost all of the computer time is wasted.
 
  • #7
Well, maybe it's a language problem. I will give it one more try.

When I say please post your problem I mean, please describe the system you are trying to solve. What material is between your source and detector? Are you doing a source calculation or a kcode calculation? That sort of thing. Just saying your stats are bad does not let me help you. I need to know about the system you want to analyze.

You have now posted some vague hints. It seems like you have an x-ray source and some detectors.

For MCNP 6.2, the user manual section 3.3.6 is where you want to start reading.

When you have a source there are a couple reasons the stats may be bad.

One is simple geometry. As you get farther from the source many of the particles go somewhere besides the detector. You can deal with this through a variety of biasing methods. You make your source point in the direction of the detector. Then you adjust the normalizing of the detector to account for the biasing. For example, a spherical source could be adjusted to only send particles in a tiny cone. Then you adjust for the relative area of the cone versus the full sphere.

Another method for geometry is the DXTRAN sphere. Before you use this one you should read the manual VERY carefully. You can get misleading results very easily if you do things wrong.

There are also a variety of detector tallies that are semi-deterministic. Again, you need to read the manual on these VERY carefully.

Another reason you may be getting bad stats is shielding. If there is a lot of material between your source and detector then nearly all the particles get absorbed before they get to your detector. There are a bunch of things you can do in that case. The simplest is adjusting the importance of various parts of the system. The goal is to have the number of particles at your detector be larger. There are several methods with additional levels of sophistication, but also additional effort required.

In very broad outline, importance adjusting goes like so. Consider a source, shielding material, and a detector on the other side.

source | shielding | shielding| shielding| shielding| detector

By the time particles get through there are very few left. Most get absorbed. The basic idea is you set the importance higher and higher as you get closer to the detector.

source | shielding | shielding| shielding| shielding| detector
imp:1 imp:1 imp:2 imp:4 imp:8 imp:16

The idea is, when importance changes from 1 to 2, the code will change one particle of weight 1 to two particles of weight 1/2. The ideal is to keep the number of particles roughly constant across each layer. That way you can get good stats at the detector.

For simple systems you can apply this by hand. For more complicated systems there are some automated utilities in MCNP. They are fairly complicated and require a lot of careful reading of the user manual.
 

1. What is MCNP5 and how is it used for statistical checks?

MCNP5 is a computer code used for simulating and analyzing the transport of particles through matter. It is commonly used in nuclear engineering and radiation physics. Statistical checks are performed on the results of MCNP5 simulations to ensure their accuracy and reliability.

2. What are the main statistical checks used in MCNP5?

The main statistical checks used in MCNP5 are the Chi-squared test, the Kolmogorov-Smirnov test, and the Anderson-Darling test. These tests evaluate the goodness of fit between the simulated results and the expected results.

3. How do statistical checks in MCNP5 help improve the accuracy of simulations?

By performing statistical checks on MCNP5 simulations, we can identify any discrepancies between the expected and simulated results. This allows us to adjust the simulation parameters and improve the accuracy of the results.

4. Are there any limitations to using statistical checks in MCNP5?

Yes, there are limitations to using statistical checks in MCNP5. These checks assume that the data follows a specific distribution, which may not always be the case. Additionally, the accuracy of the checks may be affected by the size of the simulated data set.

5. Can statistical checks in MCNP5 be automated?

Yes, statistical checks in MCNP5 can be automated using scripting or programming languages. This allows for efficient and consistent evaluation of large data sets. However, it is important to carefully review and interpret the results of automated checks to ensure their validity.

Similar threads

  • Nuclear Engineering
Replies
1
Views
3K
  • Quantum Interpretations and Foundations
Replies
9
Views
2K
  • Advanced Physics Homework Help
Replies
1
Views
1K
  • Quantum Interpretations and Foundations
2
Replies
54
Views
3K
Replies
2
Views
1K
Replies
14
Views
2K
Replies
19
Views
1K
Replies
4
Views
854
  • Set Theory, Logic, Probability, Statistics
Replies
2
Views
3K
Replies
6
Views
1K
Back
Top