Model Fuel Assembly w/ Gamma Source: Solving a Sampling Problem

In summary, the problem appears when the program tries to sample the particles. The lower the EFF parameter is when defining the source, the more time it takes to write the same error message.
  • #1
Gregorovych
4
1
Hi everyone, I'm making a fuel assembly model and I would like to have a cylindrical gamma source on each fuel rod to measure the decay heat of a fuel assembly but I'm struggling to define the source since it is in a repeated structure. This is the geometry of my model:
Level 2 : cells 1, 2 3 and 4 corresponding to a fuel pin and is defined by universe 1
Level 1 : cell 5 which is a lattice made of universe 1 and universe 3 (filled by himself +universe 1) like this: lat=1 fill=-14:0 -14:0 0:0 11111111111
11131131111u=3
Level 0 : cell 6 filled by universe 3 and cell 7 defines the outside world

Then, I defined my source by giving an discrete energy distribution (corresponding to the highest gamma peaks), the cell definition and finally the axial and radial sampling limits (corresponding to the dimensions of the fuel rod):
SDEF ERG=D1 CEL=D3:D4 RAD=D5 EXT=D6 PAR=P (I will put only the cell def for clarity)

SI3 L (4<5[u=1]<6)
SP3 1 1 1 1 1 1... (# corresponding to all fuel rods)
SI4 L 1 2 3
SP3 1 0 0

When I'm running my code, the following message appears:
" entry 3 on SI -1141636198 for independent variable cel at the last sampled position 1.20045E-01 1.24405E-02 -2.41423E-01 appears incorrect. Expire parameter is the sampling efficiency in source cell 1 is too low. bad trouble in subroutine sourcb of mcrun source particle no. 1 starting random number = 6647299061401 the sampling efficiency in source cell 1 is too low. "

I understand that there is a problem at the beginning of the simulation when the program tries to sample the particles, but I don't know how to solve this problem. I already tried to use the lower the EFF parameter when defining my source but it is only taking more time to write me the same message. I think that the problem can come from the source path because I didn't completely understood how to define the source path.

Any and all info/suggestions would be gratefully received! Thank you in advance for your response!
 
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  • #2
Your lattice should be 15 lines of 15 entries, and I see 2 lines of 11 entries, you have two SP3 cards, I'm guessing the second one should be an SP4 card? If you can't share your input file, can you cut it down until you have something you can share that produces the same error?

There are concepts here I don't understand, like lattices filled with themselves. I've dipped into the manual and the only mention of Sampling efficiency is a screaming nightmare.
 
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  • #3
Here is my input file with the same error. I looked at the manual and I really don't know how the sampling efficiency is importamt for the simulation. Thank you for your help!

C ------------------- Cell cards ----------------------
c
c ********************Fuel rod ************************
c
1 1 -10.97 -1 u=1
2 2 -0.1785 1 -2 u=1
3 3 -6.49 2 -3 u=1
4 4 -1 3 u=1
c
c ******************** Location of water rods **************
c
5 4 -1 110 -120 130 -140 lat=1 fill=-14:0 -14:0 0:0
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 3 1 1 3 1 1 1 3 1 1 3 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 3 1 1 3 1 1 3 1 1 1 1
1 1 3 1 1 1 1 1 1 1 1 1 3 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 3 1 1 1 1 1 3 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 3 1 1 1 1 1 1 1 1 1 3 1 1
1 1 1 1 3 1 1 3 1 1 3 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 3 1 1 3 1 1 1 3 1 1 3 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 u=3
c
c ******************** Assembly ************************
c
6 4 -1 -100 fill=3
7 4 -1 100 -170
8 0 170

C ------------------- Surface cards ----------------------
c
c ********************** Fuel rod ************************
c
1 RCC -10.01 -10.01 -159.5 0 0 319 0.46
2 RCC -10.01 -10.01 -159.5 0 0 319 0.475
3 RCC -10.01 -10.01 -159.5 0 0 319 0.525
c
c ********************** Box (assembly) **********************
c
100 RPP -10.725 10.725 -10.725 10.725 -159.6 159.6
c
c ********************** Lattice for box-assembly **********************
c
110 px -10.725
120 px -9.295
130 py -10.725
140 py -9.295
c
c
170 RPP -11 11 -11 11 -170 170
c

C ------------------- Data cards ----------------------
c -------------------- Source -------------------------
Mode P
NPS 1000
IMP:P 1 1 1 1 1 1 1 0
SDEF CEL=D2:D3 RAD=D5 EXT=D6 PAR=P
c
c *********************** Cell definition ***********************
c
SI2 L (4<5[u=1]<6)
SP2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
c
SI3 L 1 2 3
SP3 1 1 1
c
c *********************** Radial sampling limits ***********************
c
SI5 0 0.46
SP5 -21 2
c
c *********************** Axial sampling limits ***********************
c
SI6 -159.5 159.5
SP6 -21 0
c
c ------------------------ Materials -------------------------
c
c *********************** Uranium oxide ***********************
c
M1 92238 -0.837425 $ fresh fuel : 88.15% uranium and 11.85 % oxygen
92235 -0.044075
8016 -0.1185
c
c *********************** Helium gap ***********************
c
M2 2004 1
c
c *********************** Zirconium alloy***********************
c
M3 40090 -0.5145
40091 -0.1122
40092 -0.1715
40094 -0.1738
40096 -0.028
c
c *********************** Water (demineralised) ***********************
c
M4 1001 -0.66667
8016 -0.33333
 
  • #4
Hi,

This forum messes up formatting, and that can cause things to fail. This is fairly short and I've tried to fix them but I'm getting errors that will not go away. Could you rename your input file to add .txt at the end and then attach to a post please.

Edit, please still do that, but I note that when the version I've corrected is run in mcnp 5.1.6 or 6.1 they segfault, in mcnpx the error is the same as your error.
 
Last edited:
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  • #5
Alex A said:
This forum messes up formatting
Use [CODE] [/CODE] tags.

For example, without CODE tags,
c ********************Fuel rod ************************
c
1 1 -10.97 -1 u=1
2 2 -0.1785 1 -2 u=1
3 3 -6.49 2 -3 u=1
4 4 -1 3 u=1

and with CODE tags.
Code:
c ********************Fuel rod ************************
c
1 1 -10.97 -1 u=1
2 2 -0.1785 1 -2 u=1
3 3 -6.49 2 -3 u=1
4 4 -1 3 u=1
 
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  • #6
Thank you for your response. I have attached the input file (txt format) with the correct syntax + I used the code tags:
MCNP code:
C ------------------- Cell cards ----------------------
c
c ********************Fuel rod ************************
c
1    1  -10.97   -1       u=1
2    2  -0.1785   1 -2    u=1
3    3  -6.49     2 -3    u=1
4    4   -1       3       u=1
c
c ******************** Location of water rods **************
c
5    4   -1  110 -120 130 -140  lat=1 fill=-14:0 -14:0 0:0
                                1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
                                1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
                                1 1 3 1 1 3 1 1 1 3 1 1 3 1 1
                                1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
                                1 1 1 1 3 1 1 3 1 1 3 1 1 1 1
                                1 1 3 1 1 1 1 1 1 1 1 1 3 1 1
                                1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
                                1 1 1 1 3 1 1 1 1 1 3 1 1 1 1
                                1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
                                1 1 3 1 1 1 1 1 1 1 1 1 3 1 1
                                1 1 1 1 3 1 1 3 1 1 3 1 1 1 1
                                1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
                                1 1 3 1 1 3 1 1 1 3 1 1 3 1 1
                                1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
                                1 1 1 1 1 1 1 1 1 1 1 1 1 1 1  u=3 
c
c ******************** Assembly ************************
c
6    4   -1       -100             fill=3   
7    4   -1        100 -170             
8    0              170                 

C ------------------- Surface cards ----------------------
c
c ********************** Fuel rod ************************
c
1  RCC  -10.01 -10.01 -159.5   0  0  319   0.46 
2  RCC  -10.01 -10.01 -159.5   0  0  319   0.475
3  RCC  -10.01 -10.01 -159.5   0  0  319   0.525
c
c ********************** Box (assembly) **********************
c
100 RPP -10.725 10.725   -10.725 10.725  -159.6 159.6
c
c ********************** Lattice for box-assembly **********************
c
110 px  -10.725 
120 px   -9.295   
130 py  -10.725
140 py   -9.295
c
c
170 RPP -11 11  -11 11  -170 170
c

C ------------------- Data cards ----------------------
c -------------------- Source -------------------------
Mode P 
NPS 1000
IMP:P 1 1 1 1 1 1 1 0
SDEF CEL=D2:D3 RAD=D5 EXT=D6 PAR=P         
c
c *********************** Cell definition ***********************
c
SI2 L (4<5[u=1]<6)
SP2   1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 
      1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
      1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
      1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
      1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
c
SI3 L 1 2 3
SP3   1 1 1
c
c *********************** Radial sampling limits ***********************
c
SI5    0  0.46
SP5   -21  2
c
c *********************** Axial sampling limits ***********************
c
SI6   -159.5  159.5
SP6    -21   0
c
c ------------------------ Materials -------------------------
c
c *********************** Uranium oxide ***********************
c
M1   92238  -0.837425     $ fresh fuel : 88.15% uranium and 11.85 % oxygen
     92235  -0.044075
      8016    -0.1185
c
c *********************** Helium gap ***********************
c
M2   2004    1           
c
c *********************** Zirconium alloy***********************
c
M3   40090   -0.5145       
     40091   -0.1122
     40092   -0.1715
     40094   -0.1738
     40096   -0.028
c
c *********************** Water (demineralised) ***********************
c
M4    1001   -0.66667       
      8016   -0.33333
 

Attachments

  • fuel_assembly_model_input.txt
    3.7 KB · Views: 151
  • #7
Hello everyone,
I have found my problem :
So the basis of my cylinder is in x=-10.01 y=-10.01.
When I used the fact that POS=0 0 0, it has set the basis to x=0 y=0 z=0.
The code tries to find cell 1 (cause it is told to look for cell 1 on the CEL=d2 card) with the geometric data I
provide on the SDEF card: POS=0 0 0 RAD=D2 EXT=D3.

But it won't work out, cause cell 1 is defined with RCC, which basis is not on 0 0 0, as on the SDEF card. This is the cause of the error. The correct definition of my source is then:
MCNP::
SDEF CEL=D1 POS=-10.01 -10.01 0  RAD=D2 EXT=D3 AXS=0 0 1 PAR=2 
c
c *********************** Cell definition ***********************
c
SI1 L (1<5[u=1]<6)
SP1 D  1 204R
c
c *********************** Radial sampling limits ***********************
c
SI2 H   0  0.46
SP2 D  -21  1
c
c *********************** Axial sampling limits ***********************
c
SI3 H  -159.5  159.5
SP3 D   0      1

Thank you for your time!
 
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  • #8
Ok, I made the following changes to make the input file work in linux,
Stripped windows line endings, this may not have been needed,
SI2 line exceeded 80 char limit, so I replaced that whole block with "SI2 1",
Removed tabs that X complained about, 5.1.6 and 6.1 were fine with them.

This produced a file that roughly generated your errors.

I'm out of my depth with your source description but the part that jumped out at me after a lot of messing was "CEL=D2:D3". It seems to me that you are trying to do an intersection between two distributions. When I changed that to just D2 all the weirdness went.

Cool you have it working now!
 

FAQ: Model Fuel Assembly w/ Gamma Source: Solving a Sampling Problem

What is a model fuel assembly?

A model fuel assembly is a scaled-down representation of a nuclear fuel assembly used in nuclear reactors. It is typically used for testing and research purposes.

What is a gamma source?

A gamma source is a radioactive material that emits gamma rays, which are high-energy electromagnetic radiation. In this context, it is used to simulate the radiation emitted by nuclear fuel rods in a nuclear reactor.

What is the sampling problem in this context?

The sampling problem in this context refers to the difficulty in obtaining accurate and representative samples of the radiation emitted by a nuclear fuel assembly. This can be due to the complexity of the assembly and the potential for interference from other sources of radiation.

How does the model fuel assembly with gamma source help solve the sampling problem?

The model fuel assembly with gamma source provides a controlled and predictable source of radiation, allowing scientists to accurately measure and study the effects of radiation on the surrounding environment. This helps to overcome the challenges of obtaining accurate samples from a real nuclear fuel assembly.

What are the potential applications of this research?

This research can have various applications, including improving safety measures and protocols for handling nuclear fuel assemblies, studying the effects of radiation on the environment, and developing new technologies for nuclear energy production.

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