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Book cover for Reactor Dosimetry
ASTM Selected Technical Papers
Reactor Dosimetry
By
H Farrar, IV IV
H Farrar, IV IV
1
Symposium General Chairman Consultant Bell Canyon, California
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EP Lippincott
EP Lippincott
2
Program Committee Chairman
?
Westinghouse
?
Pittsburgh, Pennsylvania
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JG Williams
JG Williams
3
Program Committee Vice Chairman
?
University of Arizona
?
Tucson, Arizona
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DW Vehar
DW Vehar
4
Scientific Secretary
?
Sandia National Laboratories
?
Albuquerque, New Mexico
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ISBN-10:
0-8031-1899-6
ISBN:
978-0-8031-1899-7
No. of Pages:
131
DOI:
https://doi.org/10.1520/STP1228-EB
Publisher:
ASTM International
Publication date:
1994
eBook Chapter

Neutron Fluence Determination for Light Water Reactor Pressure Vessels

By
R Gold
R Gold
1
President
,
Metrology Control Corp
,
Richland, WA 99352
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Doi:
https://doi.org/10.1520/STP15102S
Page Count:
10
  • Published:
    1994

A general description of limitations that exist in pressure vessel neutron fluence determinations for commercial light water reactors is presented. Complexity factors that arise in light water reactor pressure vessel neutron fluence calculations are identified and used to analyze calculational limitations. Two broad categories of calculational limitations are introduced, namely benchmark field limitations and deep penetration limitations. Explicit examples of limitations that can arise in each of these two broad categories are presented. These limitations are used to show that the recent draft regulatory guide for the determination of pressure vessel neutron fluence, developed by the Nuclear Regulatory Commission, is based upon procedures and assumptions that are not valid. To eliminate the complexity and limitations of calculational methods, it is recommended that the determination of light water reactor pressure vessel neutron fluence be based upon experiment. Recommendations for improved methods of pressure vessel surveillance neutron dosimetry are advanced.

Keywords:
neutron fluence, light water reactor, pressure vessel, surveillance dosimetry, benchmark field, deep penetration

References

1.
Carew
,
J.F.
,
Todosow
,
M.
,
Grundl
,
J.A.
,
McGarry
,
E.D.
,
Kam
,
F.B.K.
and
Maerker
,
R.E.
,“
Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence
,” Draft Regulatory Guide DG-1025,
U.S. NRC
,
Washington, D.C.
, September,1993.
2.
Serpan
,
C. Z.
, Jr., “
Impact of USA-EURATOM Cooperative Dosimetry Research on NRC Regulation of Light Water Reactors
,” Proc. 6th ASTM-EURATOM Symposium on Reactor Dosimetry, Jackson Hole, Wyo ming, May 31 to June 6, 1987, STP 1001, 7–11, ASTM,
05
1989
.
3.
Lois
,
L.
, “
Reactor Dosimetry and Nuclear Reactor Regulation
,” Proc. 6th ASTM-EURATQM Symposium on Reactor Dosimetry, Jackson Hole, Wyoming, May 31 to June 6, 1987, STP 1001, 12–16, ASTM,
05
1989
.
4.
McElroy
,
W.N.
,
Lippincott
,
E.P.
,
Lowe
,
A.L.
, Jr., and
Hedgecock
,
P.D.
,
Condition Assessment and Surveillance of Nuclear Reactor Pressure Vessel Steels
, CASNRPVS/91-1, ASTM Standards Technology Training Course Workbook for a One-Day Workshop Sponsored by ASTM Committee E-10 on Nuclear Technology & Applications,
ASTM, 1916 Race St.
,
Philadelphia, PA 19103-1187
, Second Edition,
11
1991
.
5.
McElroy
,
W.N.
, “
ASTM LWR Surveillance Standards: Revisions and Physics-Dosimetry-Metallurgy Issues
,”
Transactions of ANS
,
64
, 487–488,
11
1991
.
6.
Maerker
,
R.E.
 and
Williams
,
M.L.
, “
Improvements in Calculational Techniques in PV Dosimetry
,”
Transactions of ANS
,
64
, 489–490,
11
1991
.
7.
Anderson
,
S.L.
, “
The Use of Reactor Cavity Neutron Dosimetry in the Assessment of PV Exposure
,”
Transactions of ANS
,
64
, 490–491,
11
1991
.
8.
Lowe
,
A.L.
, Jr., “
Role of Neutron Fluence in Reactor Vessel Integrity
,”
Transactions of ANS
,
64
, 491–492,
11
1991
.
9.
Gold
,
R.
,
Determination of Neutron Fluence for Light Water Reactor Pressure Vessels
,
Metrology Control Corporation
, 1982 Greenbrook Blvd., Richland, WA, 99352, MC2Report 93-04,
09
1993
.
10.
Gold
,
R.
, and
McElroy
,
W.N.
, “
The Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Program (LWR-PV-SDIP): Past Accomplishments, Recent Developments and Future Directions
,” Proc. 6th ASTM-EURATOM Symposium on Reactor Dosimetry, Jackson Hole, Wyoming, May 31 to June 6,
1987
, STP 1001, 44–61,
ASTM
,
05
1989
.
11.
McElroy
,
W. N.
, Ed.,
LWR-PV-SDIP: PCA Experiments, Blind Test, and Physics-Dosimetry Support for the PSF Experiments
, NUREG/CR-3318, HEDL-TME-84-1,
09
1984
.
12.
Butler
,
J. D.
,
Carter
,
M.D.
,
Curl
,
I.J.
,
Miller
,
P.C.
,
Packwood
,
A
 and
Power
,
S.
, “
Review of the Nestor Shielding and Dosimetry Improvement Programme
,” Proc. 6th ASTM-EURATOM Symposium on Reactor Dosimetry,
Jackson Hole
, Wyoming, May 31 to June6 1987, STP 1001, 295–307,
ASTM
,
05
1989
.
13.
Fabry
,
A.
,
Leenders
,
L.
,
Menil
,
R.
,
Minsart
,
G.
,
Tourwe'
,
H.
,
McGarry
,
E.D.
,
Lewis
,
T.A.
,
Barr-Wells
C.
 and
Austin
,
M.
, “
Venus PWR Engineering Mock-up: Core Qualification, Neutron & Gamma Field Characterization
,” Proc. 5th ASTM-EURATOM Symposium on Reactor Dosimetry,
Geesthacht, Germany
, September 24–28 1984, Vol
2
, 771–782,
D. Reidel Pub. Co.
,
Dordrecht
(
1985
).
14.
deWouters
,
R. M.
,
Laurent
,
D. J.
 and
D‘Hondt
,
P. J.
, “
Analysis of LWR Pressure Vessel Surveillance Dosimetry with MCBEND
,” Reactor Dosimetry, ASTM STP 1228,
Farrar
 
H.
 IV,
Lippincott
 
E. P.
,
Williams
 
J. G.
 and
Vehar
 
D. W.
, Eds.,
1994
(in press).
15.
Mossop
,
J.R.
,
Thornton
,
D. A.
 and
Lewis
,
T. A.
, “
Validation of Neutron Transport Calculations on Commercial Power Plants
,” Reactor Dosimetry, ASTM STP 1228,
Farrar
 
H.
 IV,
Lippincott
 
E. P.
,
Williams
 
J. G.
 and
Vehar
 
D. W.
, Eds.,
1994
(in press).
16.
Lippincott
,
E. P.
, “
Assessment of Uncertainty in Reactor Vessel Fluence Determination
,” Reactor Dosimetry, ASTM STP 1228,
Farrar
 
H.
 IV,
Lippincott
 
E. P.
,
Williams
 
J. G.
 and
Vehar
 
D. W.
, Eds.,
1994
(in press).
17.
Petrusha
,
L.
 and
Garat
,
C.
, “
Evaluation of the Results of the B&W Owners Group Cavity Dosimetry Benchmark Experiment
,” Reactor Dosimetry, ASTM STP 1228,
Farrar
 
H.
 IV,
Lippincott
 
E. P.
,
Williams
 
J. G.
 and
Vehar
 
D. W.
, Eds.,
1994
(in press).
18.
Gold
,
R.
 and
McElroy
,
W. N.
, “
Radiation-Induced Embrittlement in Light Water Reactor Pressure Vessels
,” Nucl Engr and Design 104, 155–174 (1987).
19.
Bachle
,
R. D.
,
Hehn
,
G.
,
Pfister
,
G.
,
Perlini
,
G.
 and
Matthes
,
W.
, “
Consistency Check Of Iron And Sodium Cross-Sections With Integral Benchmark Experiments Using A Large Amount Of Experimental Infor mation
,” Proc. 5th ASTM-EURATOM Symposium on Reactor Dosimetry,
Geesthacht, Germany
, Sept 24–28, 1984, Vol
2
, 841–848,
D. Reidel Pub.Co.
,
Dordrecht
,
1985
.
20.
Matzke
,
M.
,
Knauf
,
K.
,
Dietz
,
E.
,
Plewnia
,
A.
 and
Alberts
,
A.G.
, “
Transmission Of Neutrons of 20keV To 1 MeV Thru Iron
,” Proc. of the 7th ASTM-EURATOM Symposium on Reactor
Dosimetry, Strasbourg, France
, August 27–31, 1990, Editors
Tsotridis
 
G.
,
Dierckx
 
R.
 and
D‘Hondt
 
P.
,
Kluwer Academic Press
, 377–384,
Dordrecht
,
1992
.
21.
Kobayashi
,
K.
,
Kimura
,
I.
,
ZhaoHaun
,
L.
 and
YougQuin
, “
The 235U Fission Neutron Spectrum Adjusted With Multi-Foil Activation Data
,” Proc.of the 7th ASTM-EURATOM Symposium on Reactor Dosimetry,
Strasbourg, France
, August 27–31, 1990, Editors
Tsotridis
G.
,
Dierckx
R.
 and
D‘Hondt
 
P.
,
Kluwer Academic Press
, 263–269,
Dordrecht
(1992).
22.
Bennett
,
E. F.
,
Gold
,
R.
 and
Huber
,
R.J.
, “
Spectrum Measurements in a Large Dilute Plutonium-Fueled Fast Reactor
,” Proc. International Conference on Fast Critical Experiments and Their Analysis, p.477, ANL-7320 (1966).
23.
Gold
,
R.
,
Preston
,
C.C
,
Roberts
,
J. H.
,
DeLeeuw
,
G.
,
Fabry
,
A.
 and
Leenders
,
L.
, “
Nuclear Research Emulsion Measurements and the Observation of Proportional Counter Perturbation Factors in VENUS-1
,” Proc. 6th ASTM-EURATOM Symposium on Reactor Dosimetry,
Jackson Hole, Wyoming
, May 31–June 6 1987, ASTM STP 1001, 348–356,
1989
24.
Avery
,
A.
, “
Monte Carlo Calculations of Neutron Doses to Reactor Pressure Vessels
,” Proc. of the Topical Meeting on New horizons in Radiation Protection and Shielding, 275–282,
Pasco, Wash.
, April 26–May 1, 1992.
25.
Gold
,
R.
,
Roberts
,
J. H.
,
Ruddy
,
F. H.
 
Preston
,
C. C.
 and
Hendricks
,
C.A.
, “
Proton-recoil Emulsion Observations for Inte gral Neutron Dosimetry
,” Proc. of the IAEA Advisory Group Meeting on Nuclear Data for Radiation Damage and Safety,
Vienna
,
1981
.
26.
Gold
,
R.
,
Kellogg
,
L.S.
 and
McElroy
,
W.N.
, “
Intercomparisons of Radiometric Neutron Dosimetry
,”
LWR Pressure Vessel Surveillance Dosimetry Improvement Program: PSF Startup Experiments
, Vol.
2
, Section 3.0, NUREG/CR-3320, WHC-EP-0204,
11
1988
.
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