I am trying to use USDRAW to record the gamma rays emitted by a cylinder of aluminum after neutron irradiation for 5 years followed by cooling of 3 days? Based on the other examples in forum, I wrote the following code-
ENTRY USDRAW ( ICODE, MREG, XSCO, YSCO, ZSCO )
IF ( .NOT. LFCOPE ) THEN
LFCOPE = .TRUE.
OPEN ( UNIT = 89, FILE = “collfile2”, STATUS = ‘UNKNOWN’)
END IF
DO n=1, NP
IF (ICODE .eq. 110 .AND. KPART(n) .EQ. 7 .AND.
& MREG .LE. 100 .AND. ATRACK .GE. 1e6) THEN
WRITE(89,‘(1P,4G25.15)’)
& NCASE, JTRACK, ICODE, KPART(n), ATRACK
*& XSCO, YSCO, ZSCO, WEI(n)
END IF
END DO
RETURN
This returns an empty file. Can you please help me with the solution? I understand it can be done with USRBDX as well.
thanks & regards
saurabh
Input files
Please upload all relevant files. (FLUKA input file, Flair project file, user routines, and data files)
I suppose you adapted this user routine for your input. Note that some of the variables, like MREG, are dependent on the numbering of the regions in your simulation. So without having your input, it’s difficult to understand the problem. I suggest you make the smallest possible input which reproduces the problem with fortran file.
That said, it seems that based on your use case you do not need at all a user routine. Are you sure that using USRBDX would not solve your problem? USRBDX can also score after cooldown and can even provide double different distributions with the angle. You could even divide the space around the cylinder in multiple region to have a rough idea of the spatial distribution. Or using a cylindrical USRBIN around the cylinder would give you the precise spatial distribution.
THanks for the reply. I agree with you that one can use USRBDX or USRBIN to record the gammas. One follow up question on that- can i use the output of USRBIN as a source in the “second step“?
My main concern is that since the tube is about 4 meters long and it is getting irradiated from one end, so the induced radioactivity will not be uniform. thats why I wanted to record the emitted gammas as a function of length.
Please find the attached input file and the relevant mgdraw file. Can you please take a look why the mgdraw code is drawing a blank?
It is not clear to me if the entry USDRAW is suitable for scoring radioactive decays, at least meaning the non-prompt part selecting ICODE=110. Anyways, I understand you wish to score the residual photon fluence which implies some cooldown, meaning you would need to apply a card DCYSCORE to USRDUMP and that is not possible. We are looking into that…
In the meantime, I strongly suggest you score the activation with USRBIN. Then, in a second simulation, it is possible to use a card SPECSOUR taking the USRBIN as input which will generate primaries according to the activation map. In the first simulation, you should also score the residual radionuclide inventory in the target with RESNUCLEI. You can then simulate a radionuclide as primary using particle=ISOTOPE in the beam card, specify the primary isotope with HI-PROPE and activate radioactive decay (again in the second simulation) using RADDECAY. Would this approach solve your problem?