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ASTM Selected Technical Papers
Reactor Dosimetry: Radiation Metrology and Assessment
By
JG Williams
JG Williams
1
ASTM Program Chair
?
University of Arizona
?
Tucson, AZ
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DW Vehar
DW Vehar
2
Symposium Vice-Chair and Secretary
?
Sandia National Laboratories
?
Albuquerque, NM
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FH Ruddy
FH Ruddy
3
Symposium Chair
?
Westinghouse Science & Technology Ctr.
?
Pittsburgh, PA
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DM Gilliam
DM Gilliam
4
ASTM Program Vice-Chair
?
National Institute of Standards & Technology
?
Gaithersburg, MD
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ISBN-10:
0-8031-2884-3
ISBN:
978-0-8031-2884-2
No. of Pages:
897
Publisher:
ASTM International
Publication date:
2001

Three dimensional (3-D) neutron flux distributions are usually obtained by synthesizing the results from the two dimensional (2-D) calculations. However, 3-D neutron flux synthesis is inadequate in a complex geometry like the baffle-former plate area of a PWR plant because it spreads out along another axis that can not be expressed in 2-D geometry. 3-D neutron analyses for geometry with former plate were done with the three dimensional discrete ordinates code TORT [1]. Neutron spectra were obtained at the former plate area and various locations within the reactor vessel. These results were compared for energy above 0.1 MeV and 1.0 MeV with those of 2-D analyses.

1.
The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code
,” ORNL/TM-13221,
Oak Ridge National Laboratory
, Oak Ridge, TN.
2.
DORT Two-Dimensional Discrete Ordinates Transport Code System
,” RSIC Code Package CCC-484,
Oak Ridge National Laboratory
, Oak Ridge, TN,
11
1989
.
3.
BUGLE-96: Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications
,” RSIC Data Library DLC-185,
Oak Ridge National Laboratory
, Oak Ridge, TN,
03
1996
.
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