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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

This document outlines the measurement of neutron flux distribution for decommissioning in the Tokai Power Station. An activation foil method and direct measurement using a gas filled neutron detector were used for this purpose. A wide range of data could be obtained before stopping its commercial operation, from areas to be controlled as radioactive waste to areas that do not require treatment as radioactive waste. From the viewpoint of practical use, it was confirmed that these types of detection methods were sufficiently effective.

1.
Satoh
T.
, “
Permanent cessation of Tokai Power Plant's Operation
,” IAEA-TECDOC-1043, Technologies for gas cooled reactor decommissioning, fuel storage and waste disposal, (
09
1997
)
2.
Advisory committee for energy of Japan
, the report of subcommittee on nuclear energy of Japan “
For decommissioning of commercial Nuclear Power Plants
,” (
01
1997
)
3.
Rhoades
W. A.
, et al
, “
DOT 3.5 Two-dimensional Discrete Ordinates Radiation Transport Code
,” CCC-276, (
1977
)
4.
Croff
A. G.
, “
A user's manual for the ORIGEN2 computer code
,” ORNL/TM-7175,(
07
1980
)
5.
Currie
I. D.
,
Smith
P. N.
Shirakawa
M.
Yamamoto
T.
, “
Calculation of neutron fluxes and radioactivities in and around the Tokai-1 reactor pressure vessel
,”, IAEA-TECDOC-1043, Technologies for gas cooled reactor decommissioning, fuel storage and waste disposal IAEA-TCM, (
09
1997
)
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