MCNP6.2 BURN Problem Uranium Dioxide 4.2% Enrichment

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The discussion focuses on setting up a burn problem in MCNP6.2 using uranium dioxide with 4.2% enrichment. Key components include defining cell cards, surface cards, and data cards, with specific parameters for burn time, material composition, and power settings. The importance of omitting certain isotopes from calculations is emphasized to streamline the process. Users are advised that successful execution depends on the libraries available and the specific BOPT settings in the input file. The conversation highlights the need for proper data tables and models for accurate simulation results.
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Whenever I try to burn more than one material in any cell/assembly. I always get a fatal error saying "Models required. Cannot use memory reduction option.
The following nuclides use physics models rather than data tables:
6014. c
7016. c
8018. c
9018. c "and some other nuclides.

But the same code runs perfectly for burning one material. Can anyone suggest me anything? I've attached a random sample cell problem but the same thing also persist in the assembly calculation code.
[CODE title="Sample cell problem"]uranium dioxide with 4.2% enrichment
c Cell Cards
101 2 -0.0003922 -7 -5 6 imp:n=1 vol= 0.26195 tmp= 1.0109E-7
201 1 -10.55 7 -8 -5 6 imp:n=1 vol= 8.84672 tmp= 1.0109E-7
301 2 -0.001598 8 -9 -5 6 imp:n=1 vol= 0.288775 tmp= 1.0109E-7
401 3 -6.55 9 -10 -5 6 imp:n=1 vol= 3.64607 tmp= 1.0109E-7
501 4 -0.740582 10 -1 2 -3 4 -5 6 imp:n=1 tmp= 1.0109E-7
601 0 1 -2 3 -4 5 -6 imp:n=0

c Surface Cards
7 cz 0.060
8 cz 0.380
9 cz 0.386
10 cz 0.455
*1 px 0.6375
*2 px -0.6375
*3 py 0.6375
*4 py -0.6375
*5 pz 10
*6 pz -10

c Data Cards
BURN TIME =2.348,2.348
MAT=1,3
POWER=19.6
PFRAC=1.0,1.0
BOPT=1.0,-24,1.0
AFMIN=1E-32
Omit=1,136,6014,7016,8018,9018,53132,53133,53134,56136,56137,60146,
61146,62148,64150,64151,64153,90234,91232,31069,31071,32070,32073,
34074,34077,34078,34079,34080,34082,36085,37086,38084,38087,38088,
39090,39091,40095,41094,41095,41097,42092,42094,42096,42097,42098,
44096,44098,44099,44100,44102,44104,44105,44106,46107,47111,49113,
50113,50114,50115,50116,50117,50118,50119,50122,50123,50124,50125,
51123,51124,51125,51126,52120,52122,52123,52124,52125,52126,52128,
53130,53131,54123,54133,56130,56132,56133,56134,56135,56140,57138,
58136,58138,58139,58140,58141,58142,58143,58144,59142,59143,59145,
60150,61151,62144,62153,62154,63156,63157,65159,65160,66156,66158,
66162,66163,66164,68162,68164,68166,68167,68168,68170,32074,32076,
38089,38090,42099,42100,49115,50112,50126,51121,52130,52132,
57139,57140,60142,60144
c material card
m1 92235 -0.03701989817
92238 -0.8444062488
8016 -0.118573853
m2 2004 -1
m3 50000 -0.014
26056 -0.00165
24052 -0.001
40000 -0.98335
m4 1001 -0.1111
8016 -0.8889
Kcode 1000 1.0 10 60
Ksrc 0.4 0.0 0.0[/CODE]
 
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You need to omit the following isotopes in the burn card too and apply the omitting to all isotopes. if they are not important for your calculation.

All will work.

"23049 23052 23053 24051 25052 25053 25054 25056 25057 26053 26055 27057 28057"

BURN TIME =2.348,2.348
MAT=1,3
POWER=19.6
PFRAC=1.0,1.0
BOPT=1.0,-24,1.0
AFMIN=1E-32
OMIT=-1,149,6014,7016,8018,9018,53132,53133,53134,56136,56137,60146,
61146,62148,64150,64151,64153,90234,91232,31069,31071,32070,32073,
34074,34077,34078,34079,34080,34082,36085,37086,38084,38087,38088,
39090,39091,40095,41094,41095,41097,42092,42094,42096,42097,42098,
44096,44098,44099,44100,44102,44104,44105,44106,46107,47111,49113,
50113,50114,50115,50116,50117,50118,50119,50122,50123,50124,50125,
51123,51124,51125,51126,52120,52122,52123,52124,52125,52126,52128,
53130,53131,54123,54133,56130,56132,56133,56134,56135,56140,57138,
58136,58138,58139,58140,58141,58142,58143,58144,59142,59143,59145,
60150,61151,62144,62153,62154,63156,63157,65159,65160,66156,66158,
66162,66163,66164,68162,68164,68166,68167,68168,68170,32074,32076,
38089,38090,42099,42100,49115,50112,50126,51121,52130,52132,
57139,57140,60142,60144,
23049,23052,23053,24051,25052,25053,25054,25056,25057,26053,26055,
27057,28057
 
nukecore said:
You need to omit the following isotopes in the burn card too and apply the omitting to all isotopes. if they are not important for your calculation.

All will work.

"23049 23052 23053 24051 25052 25053 25054 25056 25057 26053 26055 27057 28057"

BURN TIME =2.348,2.348
MAT=1,3
POWER=19.6
PFRAC=1.0,1.0
BOPT=1.0,-24,1.0
AFMIN=1E-32
OMIT=-1,149,6014,7016,8018,9018,53132,53133,53134,56136,56137,60146,
61146,62148,64150,64151,64153,90234,91232,31069,31071,32070,32073,
34074,34077,34078,34079,34080,34082,36085,37086,38084,38087,38088,
39090,39091,40095,41094,41095,41097,42092,42094,42096,42097,42098,
44096,44098,44099,44100,44102,44104,44105,44106,46107,47111,49113,
50113,50114,50115,50116,50117,50118,50119,50122,50123,50124,50125,
51123,51124,51125,51126,52120,52122,52123,52124,52125,52126,52128,
53130,53131,54123,54133,56130,56132,56133,56134,56135,56140,57138,
58136,58138,58139,58140,58141,58142,58143,58144,59142,59143,59145,
60150,61151,62144,62153,62154,63156,63157,65159,65160,66156,66158,
66162,66163,66164,68162,68164,68166,68167,68168,68170,32074,32076,
38089,38090,42099,42100,49115,50112,50126,51121,52130,52132,
57139,57140,60142,60144,
23049,23052,23053,24051,25052,25053,25054,25056,25057,26053,26055,
27057,280
I already tried and this is working. can you explain it to me how could it works? bcs i face similar problem..
 
It works with that input? Not in my case
 
It will depend what libraries you have, and what BOPTS are in the input file. Potentially you can turn the advanced physics on instead. But you can't tell the program to not ignore nuclides and then not give it data tables or allow it to use models for those nuclides.
 
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