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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

Accurate assessment of neutron fluence at reactor pressure vessels and other internal components such as core shrouds is a crucial component of radiation damage studies, which are of fundamental importance in determining plant life. In recent years the Monte Carlo calculation method has become recognized as an accurate tool for such assessments. AEA Technology, through its development of the MCBEND Monte Carlo code in collaboration with BNFL, has been a key innovator in the development of the Monte Carlo method and in making these developments easily accessible to the user. Recent developments aimed at fluence modeling include a source processor, a point energy adjoint capability and geometric sensitivities. The code has been applied to fluence modeling in Magnox gas cooled reactors and PWRs for a number of years : with the work described in this paper it has now also been successfully applied to BWR fluence analysis.

1.
Miller
,
P. C.
,
Wright
,
G. A.
,
Boyle
,
C. B.
and
Power
,
S. W.
, “
The Use of an Inbuilt Importance Generator for Acceleration of the Monte Carlo Code MCBEND
” International Conference on the Physics of Reactors,
MarScille
,
1990
., pp. 124–132.
2.
Hall
,
M. C. G.
, “
DUCKPOND- a Perturbation Monte Carlo Code and its Applications
” OECD Specialists' Meeting on Nuclear Data and Benchmarks for Reactor Shielding,
Paris
,
1980
.
3.
Heffer
,
P. J. H
,
Jones
,
L. T.
,
Thornton
,
D. A.
,
Avery
,
A. F.
,
Smith
,
N. R.
and
Ziver
,
A. K.
, “
Magnox Reactor Pressure Vessel Dosimetry—A New Assessment
” 7th ASTM-EURATOM Symposium on Reactor Dosimetry,
Strasbourg
,
1990
, pp. 13–20.
4.
Lewis
,
T. A.
,
Hopper
,
S. E.
,
Mossop
,
J. R.
,
Thornton
,
D. A.
, “
The Prediction of Fast and Thermal Neutron Dose-Rates for the Pressure Vessels of Magnox Power Plants
” 9th ASTM International Symposium on Reactor Dosimetry,
Prague
,
1996
, pp. 600–607.
5.
Avery
,
A. F.
,
Chucas
,
S. J.
,
Locke
,
H. F.
and
Newbon
,
S.
Calculations of Pressure Vessel Fluence in PWRs using ENDF/B-VI Data
” 8th International Conference on Radiation Shielding,
Arlington
,
04
1994
, pp. 677–685.
6.
de Wouters
,
R. M.
,
Fontaine
,
M. P.
and
D'Hondt
,
P. J.
, “
Doel-1/2 Analysis of Surveillance Capsule and Cavity Dosimetry with MCBEND
” ANS Topical Meeting on Radiation Protection and Shielding, No.
Falmouth, Massachusetts
,
1996
, pp.203–210.
7.
Thornton
,
D. A.
,
Lewis
,
T. A
,
Mossop
,
J. R.
and
Haddock
,
S. A.
, “
Reactor Pressure Vessel Neutron Dosimetry Assessments for UK PWR Plant
”, 9th International Conference on Radiation Shielding,
Tsukuba
,
1999
(to be presented).
8.
Wright
,
G. A.
,
Avery
,
A. F.
,
Grimstone
,
M. J.
,
Locke
,
H. F.
and
Newbon
,
S.
Benchmarking JEF2.2 Data for Shielding Applications
” 8th International Conference on Radiation Shielding,
Arlington
,
04
1994
, pp. 816–823.
9.
Butler
,
J.
,
Carter
,
M. D.
,
Curl
,
I. J.
,
Miller
,
P. C.
,
Packwood
A.
and
Power
S.W.
Review of the NESTOR Shielding and Dosimetry Improvement Programme (NESDIP)
” 6th International Symposium on Reactor Dosimetry,
Jackson Hole
,
1987
, pp. 295–307.
10.
Grimstone
,
M. J.
, “
Extension of the MCBEND Monte Carlo Code to Perform Adjoint Calculations using Point Energy Data
”, ANS Radiation Protection and Shielding Division Topical Conference,
Nashville
, April 19–23, 1998, pp. 143–150.
11.
Shuttleworth
,
E.
,
Grimstone
,
M.J.
and
Chucas
,
S. J.
, “
Application of Acceleration Techniques in MCBEND
” 9th International Conference on Radiation Shielding,
Tsukuba
,
1999
(to be presented).
12.
Halsall
,
M. J.
, “
WIMS8—Speed with Accuracy
” International Conference on the Physics of Reactors,
Long Island
,
1998
, pp103–108.
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