Re: How to simulate URANIUM 235?

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Maybe because the region of the residual nuclei scoring is not defined?

For the other questions (1 and 2), the only way I see is using an
external source routine, sampling from the fission product yield.

Bye!

Il 11/01/2013 12:17, vahan petrosyan ha scritto:
> Thanks it worked! :)
>
> but it doesn't work for RESNUCLEi card I still get errors: "empty data
> set" why? :(
>
> I also tried to implement second method ie. to bombard uranium target
> with neutrons.
> 1) Is it possible to get Correct Equivalent dose not only from GAMMA
> but other fission fragments (if alpha is not possible then at least
> electromagnetic part) of URANIUM235 with the second method?
> (Francesco's second note)
> 2) Generally how one can calculate other fission fragments
> contribution of U235 into dose with FLUKA?
> 3)Can you list please what kind of similar limitations have fluka,
> especially with dose calculations? (in order to be careful)
>
> Thanks!
>>
>> On 11.01.2013 12:26, sarchia wrote:
>>> Thank you Francesco for your answer, I missed many points!
>>>
>>> Dear Vahan, the way I suggested and that you are using in your input
>>> file only takes into account the gamma emission during uranium
>>> decay. You see zeros in the USRBIN file and empty RESNUCLEi file
>>> because in the DCYSCORE card WHAT(1) must be = -1.0 (check the manual).
>>>
>>> Lucia
>>>
>>>
>>>
>>> Il 11/01/2013 07:51, vahan petrosyan ha scritto:
>>>> Thanks for your Attentions!
>>>> I tried to implement Lucia's mentioned first method but as usual
>>>> happens to me I have problems:) I GET ALL ZEROES when plotting
>>>> USRBIN plotes and EMPTY data set for RESNUCLEI plot.
>>>>
>>>> I attached my input file, If you can please take a look.
>>>>
>>>> Thanks!
>>>>
>>>>
>>>>
>>>>
>>>>
>>>> On 10.01.2013 23:04, Francesco Cerutti wrote:
>>>>>
>>>>> Hi,
>>>>>
>>>>> be careful:
>>>>>
>>>>> i. for alpha emitters, as already pointed out
>>>>> (http://www.fluka.org/web_archive/earchive/new-fluka-discuss/4853.html),
>>>>> the present FLUKA version does NOT generate at all decay alphas,
>>>>> but lets the isotope decay and transport only electromagnetic
>>>>> particles emitted along the decay chain.
>>>>>
>>>>> ii. no low energy (<20MeV) induced fission is explicitly
>>>>> simulated, since the multigroup treatment applies. This means that
>>>>> fission fragments are just separately sampled for residual nuclei
>>>>> scoring purposes, but they are not at all transported and the
>>>>> interaction of a given energy group neutron with a given material
>>>>> isotope yields, in terms of energy deposition, a fixed kerma value
>>>>> averaged over all the open reaction channels
>>>>>
>>>>> Happy New Year
>>>>>
>>>>> Francesco
>>>>>
>>>>> **************************************************
>>>>> Francesco Cerutti
>>>>> CERN-EN/STI
>>>>> CH-1211 Geneva 23
>>>>> Switzerland
>>>>> tel. ++41 22 7678962
>>>>> fax ++41 22 7668854
>>>>>
>>>>> On Thu, 10 Jan 2013, sarchia wrote:
>>>>>
>>>>>> Il 10/01/2013 13:47, vahan petrosyan ha scritto:
>>>>>>> Hi everyone! :)
>>>>>>>
>>>>>>> I have may be simple but for me important questions.
>>>>>>> How one can simulate URANIUM 235 decay?
>>>>>>>
>>>>>>> If I have 1gramm Uranium 235 what Dose it will produce. Is it
>>>>>>> possible
>>>>>>> to do by fluka?
>>>>>>>
>>>>>>> Or I should take fission fragments as primaries and do for each
>>>>>>> them
>>>>>>> separate simulation?
>>>>>>>
>>>>>>> Is it possible to define two separate beams in fluka in the same
>>>>>>> input?
>>>>>>> Thanks!
>>>>>>>
>>>>>>>
>>>>>>
>>>>>> Hi,
>>>>>>
>>>>>> URANIUM 235 is an alpha emitter and FLUKA can simulate its decay
>>>>>> using
>>>>>> the BEAM card with ISOTOPE as SDUM; with HI-PROPE card you
>>>>>> specify Z and
>>>>>> A of the element. Then you have to activate the decay mechanism
>>>>>> through
>>>>>> the RADDECAY card (semi-analogue mode), and add a DCYSCORE card to
>>>>>> associate the decay and the scoring. Results will be given
>>>>>> normalized
>>>>>> per one disintegration.
>>>>>>
>>>>>> U-235 does not go spontaneous fission, so in case you want to
>>>>>> simulate
>>>>>> the fission process, in my opinion, you should define a neutron beam
>>>>>> impinging on a Uranium target.
>>>>>>
>>>>>> In general, you can use separate beams in one simulation using an
>>>>>> external source routine edited according to your needs.
>>>>>> I hope I have answered your questions.
>>>>>> Cheers,
>>>>>>
>>>>>> Lucia
>>>>>>
>>>>>>
>>>>>>
>>>>
>>>
>>
>
Received on Thu Jan 17 2013 - 09:28:06 CET