SINBAD ABSTRACT NEA-1517/61
SBE 1.012

 
1. Name of Experiment:  

SDT5. Stainless Steel Broomstick Experiment - An Experimental Check of Neutron Total
Cross Sections - 1968

2. Purpose and Phenomena Tested:  

This experiment was designed to test a given set of neutron total cross sections for
oxygen in the range of 1.2 - 11.0 MeV.
  
3. Description of the Source and Experimental Configuration:  

The source used was the Tower Shielding Reactor II (TSRII) at the Tower Shielding 
Facility located in Oak Ridge National Laboratory. A 3.5-inch beam of neutrons 
emerged from the 4-inch collimator made of water and lithiated paraffin. The 8-inch 
sample of stainless steel was placed approximately 50 feet away from the source, 
lengthwise in the neutron beam and housed behind a 4-foot-thick water shield with a 
3.5-inch-diameter hole concentric to the beam and stainless steel sample. The 
detector was placed approximately 50 feet behind the sample and was shielded with 
water and lead. The purpose for the distance between source, sample and detector was
to minimize in scattered neutrons mixing with the uncollided neutron spectrum.

4. Measurement System and Uncertainties:  

The measurements were made with a NE-213 spectrometer, with a 2-in. x 2-in. active 
fluid cylinder. A modified Forte circuit separated the neutron from the gamma-
induced pulses. Unfolding the pulse-height distributions was accomplished by using 
the FERDoR computer code. The data uncertainty is due to statistical collections and
a 5-10% error in power calibration. The data is unfolded into a 68% uncertainty 
range (high and low) for flux values, excluding the power calibration error.
  
5. Description of Results and Analysis:  

The data was collected for a bare beam, (stainless steel sample removed, lead left 
in place) to collect a source spectrum, for use in the calculated uncollided 
spectrum. Data was then collected for a 8-inch-wide x 4-inch-diameter oxygen sample.
The density of the sample was 0.0436 atoms/barn-cm and was considered to be one of 
two possible compositions, taken from different references, since no chemical 
analysis was performed on the SS sample.  

6. Special Features:
  
None

7. Author/Organizer  
  
Experiment:
    C.E. Clifford, E.A. Straker, F.J. Muckenthaler, V.V. Verbinski, R.M. Freestone, 
    Jr., K.M. Henry, and W.R. Burrus, 1967
    
Analysis: 
    R.E. Maerker ORNL TM 3871 (in reference to E.A. Straker ORNL TM 2242)

Compiler of data for SINBAD: 
    Hamilton Hunter, Radiation Shielding Information Center, Oak Ridge National 
    Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6362, fax 423-574-6182, e-mail 
    h3o@ornl.gov.

Reviewer of compiled data: 
    C.O. Slater, Nuclear Analysis and Shielding Section, Computational Physics and 
    Engineering Division, Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, 
    TN 37831-6363.

8. Availability:  
   
Unrestricted
  
9. References:  

[1] C.E. Clifford, E.A. Straker et al., "Measurements of the Spectra of Uncollided 
    Fission Neutrons Transmitted Through Thick Samples of Nitrogen, Oxygen, Carbon,
    and Lead: Investigation of the Minimum Total Cross Sections," Nucl. Sci. Eng. 
    27 , 299 (1967).
[2] E.A. Straker, "Experimental Evaluation of Minima in the Total Neutron Cross 
    Sections of Several Shielding Materials," ORNL TM 2242, June 1968.
[3] R.E. Maerker, "SDT5. Stainless-Steel Broomstick Experiment-An Experimental Check
    of Neutron Total Cross Sections," ORNL TM 3871, Sept., 1972.
[4] R.M. Freestone, Re-unfolding of original NE-213 Spectrometer results using FERD,
    est 1988, compiler acquired via private communication w/ D.T. Ingersoll, 5/96.
[5] R.E. Maerker and F.J. Muckenthaler, "The Absolute Neutron Spectrum emerging through 
    a 15-1/4-IN.Collimator from the TSR-II Reactor at the Tower Shielding Facility," 
    ORNL-TM-4010.

10. Data and Format:  

Tables:  
    (1) Neutron Source Spectrum (measured without sample, with lead in place)
    (2) Composition of Type-310 Stainless Steel
    (3) 8-inch-Stainless Steel Broomstick Measurements in Energy (MeV) and Flux
        (neuts/(cm2-MeV-min-W))
  
Figures: 
    (1) Schematic of Experiment
    (2) Neutron Source Spectrum (measured without sample, with lead in place)


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SINBAD Abstract Generation Date: 06/98

SINBAD Abstract Last Update: 06/98