Student Practice in JINR Fields of Research, Dubna 2011
Speaker: Klara Rusin
University of Lodz
Laboratory of Information
Technologies (LIT),Dubna
Supervisor :
Dr Andrzej Wojciechowski
Student:
Klara Rusin (Poland)
The name of the project :
Energy and Transmutation of
Radioactive Wastes (E+T RAW)
The main goal of this research program is transmutation
of radioactive waste of energetic reactors and using it to
energy production
Experiment took place in march 2011 in JINR Dubna
Members of a group :
Russia (JINR Dubna, CPTP Atomenergomash, Moscow,
Russia, Obmińsk)
Belaruss, Poland, Czech Republic, Germany, France,
Greece, Mongolia, Ukraine, Australia.
The coordinators:
•M.Kadykov, S.Tyutyunnikov,( JINR)
•V.Chilap, (CPTP ”Atomenergomash”)
Research the fission of 238U
nucleus in fast neutron beam
• Research spectrum of amount
neutron energy
• Plutonium production
•
To mesurement was used track
and activaton detector, which was
located in aluminium plates in
different distance from axis beam
There was used deuteron beam
accelerated to 2 GeV, 4 GeV, 6
GeV in LHE nucleotron in Dubna
The results from activation detectors
was obtain using germanium
detectors to measure the energy
gamma spectrum.
Number of fissions defines by
averaging of following fission product
yields:
97Zr (5.42%), 131I (3.64%), 133I
(6.39%), 143Ce (4.26%)
Measuring
system
Measuring
system
Detector Geometry
Red – U238
Blue- detector
Calculation method
To calculate number of 238U(n,f) reaction Nf was
used definition:

(1)
N f    ( E ) ( E )dE
0
Where φ(E) density of neutron flux calculated by
MCNPX 2.6 based on NDF Data Base,
σ(E) –cross section from JENDL (Japanese Evaalueted
Nuclear Data Library )
In calculation was used :
•Beam profle parameters from
proportional chamber.
•MCNPX 2.6 code
ENDF –Evalueted Nuclear Data File
 Bertini + FLUKA + Abla
•Formula (1) and the U-238(n,f) cross
section from JENDL data library
The U-238(n,f) cross section from JENDL Data Base.
Fig Comparison neutron production for experiment and models of MCNPX code. Target is
made with natPb. Width and diameter of target is equal 35cm and 15cm respectively.
Experimental data are from Phys.Rev.C56:1909-1917,1997.
The experimental data presented in this work are from:
J.Adam, A.Baldin, N.Vladimirova, N.Gundorin, B.Gus’kov, M.Kadykov,, et al.,
Preliminary results of March Nuclotron run on «QUINTA» setup, ,JINR,2011,Dubna
SSNT: Solid State Neutron Truck
Axial distribution. Comparison of SSNT , Activation methods and calculation
results for R=4cm, beam energy 2 , 4 and 6 GeV
Radial distribution. Comparison of SSNT, Activation methods and calculation
results for Z=36cm, beam energy 2 , 4 and 6 GeV.
Axial distribution. Comparison of SSNT , Activation methods and
calculation results for R=8cm, beam energy 2 , 4 and 6 GeV
Axial distribution. Comparison of SSNT , Activation methods and calculation
results for R=12cm, beam energy 2 , 4 and 6 GeV
Number of fission of U-238
calculated by
Bertini+FLUKA+ABLA code quite
agree with experimental data.
The differences between
experimental data and calculation
results includes in the range of
experimental errors (about 7%).
For The Curious
[1] FLUKA for inelastic collisions of hadrons use difference model
- for range 0.02-2.5GeV - preequilibrium model,
- for range 2.5-4GeV - resonance production and decay model,
- for range 4GeV-20TeV -Dual Parton Model) .
(www.fluka.org)
The Bertini model [2,3] and FLUKA codes are swiched at 1.5GeV for
nucleons and pions.
(The Bertini model was used below 1,5GeV and the FLUKA highenergy generator will be used abow this value)
[1] www.fluka.org
[2] V.SBarashenkov,V.D.Toneev, Vzaimodeistvie
vysokoenergeticheskih chastits i atomnyh yader s
yadrami,Atomizdat,1972.
[3] N.W.Bertini et al., Phys.Rev. 1976, V. C14,P.590.
[4] L. Dresner, “EVAP-A Fortran Program for Calculating the
Evaporation of Various
Particles from Excited Compound Nuclei,” Oak Ridge National
Laboratory report
ORNL-TM-7882 (July 1981).