SINBAD ABSTRACT NEA-1553/43

Juelich Li Metal Blanket Experiment (1976 - 1984)

1. Name of Experiment:

Juelich Neutronics Lithium Metal Blanket Experiment (1976 - 1984)

2. Aim of the experiment:

The neutronics experiments were performed to validate involved neutron cross sections, especially
for tritium production.    

3. Description of the Source and Experimental Configurations:

A 14-MeV-fusion-neutron source (deuterium ions accelerated on to a T/Ti/Cu 
target) at Institut for Reactor Developement (IRE) in Juelich was used to perform 
measurements of the tritium production with the aid of activation techniques and TLD detectors. 
The space dependent neutron spectra, and energy deposition [3] are determined as well.
Several experimental configurations were tested. With/without inner Be neutron multiplication layer  
and outer Graphite reflector (Figure 7);
Li configuration - only Li blanket,
Be-Li configuration - Li blanket with Be inner layer,
Li-C configuration - Li blanket with outer graphite reflector,
Be-Li-C configuration - Li blanket with both Be and C layers.

4. Measurement Systems and Uncertainties:

Li2CO3  samples, TLD detectors and activation foils were placed along
the central perpendicular to the model axis experimental channel.
Several irradiations sessions were performed in the range 1014 to 1016  14 MeV source neutrons.
Tritium activity was measured by liquid scintillation method [6], gas counting method [5]
and the use of LiF TLD detectors [3], [4].
Foils activity were recorded from calibrated Ge(Li) detectors.
Errors from counting statistics, uncertainty of detector calibrations, 
are negligible comparing with the source intensity uncertainty(15-20%).  
A set of TLD-100/600/700 detectors were used for measuring the nuclear heating as a 
function of radius inside the blanket. These were calibrated by a 137Cs source.  
For the liquid scintillation method, foil activation and TLD measurements neutron source intensity 
was measured by the activation method with the uncertainty 
of the 58Ni(n,2n)57Ni and 19F(n,2n)18F cross sections of 15-20%.
For gas counting method 23Na(n,2n)22Na and 89Y(n,2n)88Y reactions
were used. Uncertainty in these cross sections are bigger - 20-30%. 

5. Description of Results and Analysis:

Li2CO3 samples in Al sample holders, TLD detectors and activation foils were placed at different 
distances from the model axis(10 to 60 cm, to 73 cm in graphite reflector).
Results  are given with the  random error. Systematic errors are due to the uncertainty of the 
activation cross sections used for neutron source intensity measurements. MORSE code was used 
to compute tritium production rates in Li.
As original Morse input is not available, recently a simplified MCNP inputs for each configuration 
(Li, Be-Li, Be-Li-C,Li-C),are constructed (Figure 7) and some of the results are here presented.
The experimental results of the tritium production, and saturation activities are compared with 
MCNP and FISPACT calculations.   

6. Special Features:

None

7. Author/Organizer:

  Experiment and analysis:
G.Gyorgen, R.Herzing, L.Kuijpers, W.Pohorecki 
   
 Compiler of data for SINBAD:

Wladyslaw Pohorecki, Faculty of Physics and Applied Computer Sciences, AGH University 
of Science and Techniques, Kraków Poland, TN +48 12 6172954, fax +40 12 6340010, 

Review of compiled data: to be carried out
 

8. Availability:

Unrestricted

9. References:

[1]    L. Kuijpers, "Experimental Model Studies for a Fusion Reactor 
       Blanket", KFA Juelich Report 1356(1976) 
[2]    L. Herzing,  " Erprobung neutronenphysikalischer Rechenverfahren 
       on Lithiumblanketmodellen fuer einen Fusionsreaktor",  KFA Juelich Report 1357(1976)
[3]    G. Gyorgen, KFA Juelich Report 2060(1986).
[4]    W. Pohorecki, "Diagnostics of some parameters of a fusion reactor
       blanket model",  AGH MIFiTJ Report INT 239/PS ISSN 0302-9034, Cracow 1989 (in polish).
[5]    S. M. Quaim, R. Woelfle, G. Stoecklin, "Radiochemical Methods in the determination of 
       Nuclear data for Fusion Reactor Technology", Journal of Radioanalytical Chemistry, 
       Vol. 30 (1976) 35-51
[6]    R. Dierckx, Nucl. Instr.& Meth. 107,397  (1973).
[7]    G. Gyorgen, W. Pohorecki, J. M. Zazula, "Calculation of the LiF TLD's Kerma Factors 
       for Estimation of their Neutron Responses in a Lithium Blanket Model", KFA-IRE-IB-20/84
[8]    P. Cloth, D. Filges, K. H. Hammelmann and N. Kirch, "A Homogenious Lithium-Metal Cylinder
       for CTR-Blanket Experiments", Nuclear Instruments and Methods, 124 (1975) 305-306
[9]    R. Herzing, L. Kuijpers, P. Cloth, D. Filges, R. Hecker and N. Kirch, "Experimental and
       Theoretical Investigations of Tritium Production in a Controlled Thermonuclear Reactor
       Blanket Model", Nuc. Sci. Eng., 60, 169-175 (1976)
[10]    R. Herzing, L. Kuijpers, P. Cloth, D. Filges, R. Hecker and N. Kirch, "The Tritium
       Production in a Controlled Thermonuclear Reactor Blanket Model with a Graphite Reflector",
       Nuc. Sci. Eng., 63, 341-343 (1978)
[11]   R. Hecker, P. Cloth, D. Filges, "Survey on Experimental Neutron Physics of CTR Blankets
       in the KFA", Proceedings of the 9th Symposium on Fusion Technology 1976, EUR-5602,
       pp.551-556; CONF-76063 
[12]   P. Cloth, D. Filges R. Herzing, N. Kirch, , "Neutron Multiplication Effect of CTR Blankets
       Containing Beryllium", Proceedings of the 9th Symposium on Fusion Technology 1976, EUR-5602,
       pp.569-575; CONF-760631


10. Data and Format:

Tables:

Tab. (1) Properties of the activation detectors used in the model blanket experiment.
Tab. (2) Measured saturation activities around neutron generator target(R=0.100 m), on the inner
         blanket surface (R=0.100 m) and in the blanket (R=0.308 m) [2].
Tab. (3) Measured saturation activities in the blanket(R=0.528 m), on the inner Be multiplier
         surface (R=0.055 m) and on the inner blanket surface(R=0.100 m)- Be multiplier present [2].
Tab. (4) Measured saturation activities in the blanket(R=0.149 m, R=0.308 m R=0.528 m) - Be multiplier
         present.
Tab. (5) Measured saturation activities in the Carbon reflector(R=0.689 m) - Be multiplier not present
         and in the Carbon reflector(R=0.689 m) - Be multiplier present.
Tabs. (6,6a,6b) Measured with use of LSC and radiochemical methods and calculated tritium production
         reaction rates in natural Li (Li configuration) 
Tabs. (7,7a) Measured with use of LSC and calculated tritium production reaction rates in 6Li and 7Li
         (Li configuration)
Tabs. (8,8a) Measured with use of LSC and calculated tritium production reaction rates in Li blanket
          with graphite reflector
Tabs. (9,9a) Measured with use of LSC and calculated tritium production reaction rates in Li blanket
          with inner Be multiplier
Tab. (10) Measured with use of LSC and calculated tritium production reaction rates in Li blanket 
          with inner Be multiplier and graphite reflector
Tab. (11) Saturation activities calculated in the simplified blanket model (Li configuration) with
          the use of MCNP and FISPACT.
Tab. (12) Saturation activities calculated in the simplified blanket model (Be-Li configuration) with
          the use of MCNP and FISPACT.
Tab. (13) Saturation activities calculated in the simplified blanket model (Li-C configuration) with
          the use of MCNP and FISPACT.
Tab. (14) Saturation activities calculated in the simplified blanket model (Be-Li-C configuration) with
          the use of MCNP and FISPACT.

Figures

Figure 1 - Li Blanket Sketch
Figure 2 - The Li blanket layout.
Figure 3 - The Li blanket layout with accelerator.
Figure 4 - The Li blanket layout with graphite reflector.
Figure 5  - Inner berylium multiplier sketch
Figure 6 - Target support sketch
Figure 7 - MCNP input 

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SINBAD Benchmark Generation Date: 11/2008
SINBAD Benchmark Last Update: 11/2008