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ASTM Selected Technical Papers
Reactor Dosimetry: Methods, Applications, and Standardization
By
H Farrar, IV IV
H Farrar, IV IV
Program Chairman and Co-Editor
1
Rockwell International
?
Canoga Park, California
Search for other works by this author on:
EP Lippincott
EP Lippincott
Program Vice Chairman and Co-Editor
2
Westinghouse
?
Pittsburgh, Pennsylvania
Search for other works by this author on:
ISBN-10:
0-8031-1184-3
ISBN:
978-0-8031-1184-4
No. of Pages:
815
Publisher:
ASTM International
Publication date:
1989

A procedure has been developed to use the SANDII spectrum adjustment code to generate satisfactory neutron spectra in a manner that does not require initial trial functions that approximate the real spectra. Thus a spectrum can be determined primarily by a set of foil activation data, and a priori calculations of a trial spectrum or detailed knowledge about the experiment environment are not required. The reduction in the amount of information required facilitates interlaboratory comparisons and the efficiency of the spectrum generation process. Examples are provided, and a discussion is included that considers conditions under which the procedure can be expected to yield acceptable results.

1.
Berg
,
J.
and
McElroy
,
W. N.
,“
A Computer-Automated Iterative Method for Neutron Flux Spectra Determination by Foil Activation
,”
Atomics International
Tech. Rep. No. AFWL-TR-67-41.Canoga Park, Calif.,
09
1967
.
2.
Oster
,
C. A.
 et al
,“
A Modified Monte Carlo Program for SANDII with Solution Weighting and Error Analysis
,” HEDL-TME 76-60,
Hanford Engineering Development Laboratory
. Richland, Wash.,
08
1976
.
3.
Schmittroth
,
F.
,“
FERRET Data Analysis Code
,” HEDL-TME 79-10,
Hanford Engineering Development Laboratory
, Richland. Wash.,
09
1979
.
4.
Perey
,
F. G.
,“
Least-Squares Dosimetry Unfolding: The Program STAY'SL
,” ORNL/TM-6062, ENDF-254,
Oak Ridge National Laboratory
, Oak Ridge. Tenn.,
09
1979
.
5.
Stallmann
,
I. W.
,“
LSL-M2: Least Squares Logarithmic Adjustment of Neutron Spectra
,”
RSK Periferal Shield Routine Collection
, ORNL/TM-9933,
Oak Ridge National Laboratory
. Oak Ridge, Tenn.,
03
1986
.
6.
Kelly
,
J. G.
and
Vehar
,
D. W.
,“
Measurement of Neutron Spectra in Varied Environments by the Foil Activation Method with Arbitrary Trials
,” SAND87-1330,
Sandia National Laboratories
, Albuquerque, N.M.,
12
1987
.
7.
Korn
,
G. A.
and
Korn
,
T. M.
,
Mathematical Handbook for Scientists and Engineers
,
McGrawHill
,
New York
,
1961
.
8.
Obtained from
Flanders
M.
, White Sands Missile Range, N.M.
9.
Zijp
,
W. L.
,
Nolthenius
,
H. J.
,
Rieffe
,
H. Ch.
,“
Multigroup Cross Sections in SANDII Format for Spectral, Integral, and Damage Analysis
,” DOSDAM81-82, DLC-97,
Oak Ridge National Laboratory, RSIC Data Library Collection
,Oak Ridge, Tenn.,
12
1981
.
10.
Comment from
Williams
J.
,
University of Illinois
, Urbana,
1987
.
11.
Verbinski
,
V. V.
,
Cassapakis
,
C.
,
Pease
,
R. L.
, and
Scott
,
H. L.
,“
Transistor Damage Characterization by Neutron Displacement Cross Section in Silicon: Experimental
,”
Nuclear Science and Engineering
, Vol.
70
,
1979
, pp. 66–70.
12.
Luera
,
T. F.
,
Kelly
,
J. G.
,
Stein
,
H. J.
,
Lazo
,
M.
,
Lee
,
C. E.
, and
Dawson
,
L. R.
,“
Neutron Damage Equivalence in Silicon, Silicon Dioxide and Gallium Arsenide
,”
IEEE Transactions on Nuclear Science
, Vol.
NS-34
, No.
6
,
12
1987
, p. 1557.
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