Abstract

Reactor dosimetry (RD) is a tool that provides data for neutron fluence accumulated over the reactor pressure vessel (RPV) during the reactor operation. This information, however, is not sufficient for RPV lifetime assessment. The life management of RPV is a multidisciplinary task. To assess whether the RPV steel properties at the current stage (for actual accumulated neutron fluence) of reactor operation are still “safe enough,” the dependence of material properties on the fluence must be known; this is a task for material science (MS). Moreover, the mechanical loading over the RPV during normal operation and accidences have to be known, as well, for evaluation, if the RPV material integrity in this loading condition and existing cracks is provided. The crack loading path in terms of stress intensity factor is carried out by structural analyses (SA). Pressure and temperature distribution over RPV used in these analyses are obtained from a thermal hydraulic (TH) calculation. The conjunction of RD and other disciplines in RPV integrity assessment is analyzed in accordance with the FFP (fitness for purpose) approach. It could help to improve the efficiency in multi-disciplinary tasks solutions.

References

1.
Ilieva
,
K.
,
Belousov
,
S.
,
Ballesteros
,
A.
,
Osmera
,
B.
, and
Zaritsky
,
S.
, “
Reactor Dosimetry for VVERs RPV Lifetime Assessment
,”
Prog. Nucl. Energy
, Vol.
51
, January
2009
, pp.
11
13
.
2.
Ilieva
,
K.
,
Belousov
,
S.
,
Ballesteros
,
A.
, and
Zaritsky
,
S.
, “
Reactor Dosimetry for VVERs: Past and Future
,”
Nucl. Eng. Int.
, Vol.
55
, August
2010
, pp.
13
19
.
3.
Guidelines on Pressurized Thermal Shock Analysis for VVER Nuclear Power Plant
,” Report No. IAEA-EBP-WWER-08/Rev. 1, IAEA, Vienna,
2006
4.
Regulations and Calculation Norms for Equipment and Tubing Strength of the Nuclear Energy Facilities
,” Report No. PNAE G-7-002-86, PNAE G-7-008-89, Energoatomizdat, Gosatomnadzor of Russia, Moscow (in Russian),
1989
.
5.
Rhoades
,
W. A.
, and
Childs
,
R. L.
, “
TORT Three-Dimensional Discrete Ordinate Neutron/Photon Transport Code with Space-Dependent Mesh and Quadrature
,” ORNL-6268, or DOORS3.2, RSICC ORNL, Code Package CCC-650 (
1987
).
6.
Briesmeister
,
I. F.
, Ed.,
MCNP -A General Monte Carlo N-Particle Transport Code
, version 4C, LA-13709-M, RSICC ORNL, Code Package, CCC0700 (
2000
).
7.
White
,
J. E.
,
Ingersoll
,
D. T.
,
Slater
,
C. O.
, and
Roussin
,
R. W.
, “
BUGLE96, A Revised Multigroup Cross-Section Library for LWR Applications Based on ENDF/B-VI Released 3, ORNL-7795
,”
Proc. RP&S
, No. Falmouth, MA,
1996
, pp.
1071
1079
.
8.
Bucholz
,
J. A.
,
Antonov
,
S. A.
, and
Belousov
,
S. I.
, “
BGL440 and BGL1000 Broad Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data
,” IAEA Report No. INDC(BUL)-15, Distrib.:G,
1996
.
9.
Ballesteros
,
A.
,
Jardí
,
X.
,
Böhmer
,
B.
,
Konheiser
,
J.
,
Ošmera
,
B.
,
Kyncl
,
J.
,
Keresztúri
,
A.
,
Hordosy
,
G.
,
Ilieva
,
K.
,
Belousov
,
S.
,
Kirilova
,
D.
,
Mitev
,
M.
,
Petrov
,
B.
,
Acosta
,
B.
,
Smutný
,
V.
,
Polke
,
E.
,
Zaritsky
,
S.
,
Töre
,
C.
, and
Ortego
,
P.
, “
Reactor Dosimetry: Accurate Determination and Benchmarking of Radiation Field Parameters, Relevant for Pressure Vessel Monitoring (REDOS)
,” AMES Report No. 17, EUR 21771 EN, http://safelife.jrc.nl/ames/publications/index.php.,
2005
.
10.
Zaritsky
,
S.
,
Belousov
,
S.
,
Brodkin
,
E.
,
Egorov
,
A.
,
Ilieva
,
K.
,
Kam
,
F. B. K.
,
Krysl
,
V.
,
Osmera
,
B.
,
Smutny
,
V.
,
Valenta
,
V.
, and
Zaritskaya
,
T.
, “
WWER-440 Pressure Vessel Dosimetry Benchmarks: Calculations and Analysis, Volume. I, Technologies for the New Century
,”
ANS Radiation Protection and Shielding Division Topical Conference
,
Nashville, Tennessee
, April 19–23,
1998
, pp.
425
432
.
11.
Belousov
,
S.
,
Ilieva
,
K.
, and
Kirilova
,
D.
, “
Conformity between LR0 Mock-Ups and VVERs NPP RPV Neutron Flux Attenuation
,”
Reactor Dosimetry, Proc. of the 13th International Symposium on Reactor Dosimetry
,
2009
, pp.
250
257
.
12.
Borodkin
,
G. I.
, etal., “
Safety Guide. Procedure of Neutron Dosimetry on the Ex-Vessel Surface of VVER of NPP (RB-018-01)
,”
Gosatomnadzor of Russia
, November
2001
(in Russian).
13.
Belousov
,
S.
,
Ilieva
,
K. R.
, and
Matushko
,
V.
, “
Sensitivity Analysis and Neutron Fluence Adjustment for VVER-440 RPV
,”
Reactor Dosimetry, Proc. of the 14th International Symposium on Reactor Dosimetry
,
ASTM International STP1490
,
West Conshohocken, PA
, May
2008
, pp.
333
339
.
14.
Belousov
,
S.
,
Ilieva
,
K. R.
, and
Kirilova
,
D.
,
Sensitivity Analysis and Neutron Fluence Adjustment for RPV VVER-1000, Reactor Dosimetry in the 21st Century, 11th International Symposium on Reactor Dosimetr
,.
World Scientific
,
Singapore
,
2003
, pp.
436
443
.
15.
Serén
,
T.
, “
Completion of the New Surveillance Programme for Loviisa 1. Use of RPV Dosimetry Benchmark’s Results for Determining Radiation Embrittlement Damage
,”
Workshop RADE
,
Bansko
,
Bulgaria
, April 1–8,
2006
.
16.
Hógel
,
J.
, “
Ex-Vessel and Retrospective Dosimetry of VVER Pressure Vessels. Use of RPV Dosimetry Benchmark’s Results for Determining Radiation Embrittlement Damage
,”
Workshop RADE
,
Bansko
,
Bulgaria
, April 1–8,
2006
.
17.
Ilieva
,
K.
,
Belousov
,
S.
, and
Apostolov
,
T.
, “
Testing of Multigroup Neutron Cross Section Libraries on Neutron Transmission through VVER-440 Vessel
,”
Nucl. Sci. Eng.
, Vol.
131
,
1999
, pp.
282
285
.
18.
Ilieva
,
K. D.
,
Belousov
,
S. I.
,
Apostolov
,
T. G.
, and
Monev
,
M.
, “
Reactor Dosimetry in the Surveillance Program of Kozloduy NPP Reactor Pressure Vessels
,”
Reactor Dosimetry: Radiation Metrology and Assessment
,
J. G.
Williams
,
D. W.
Vehar
,
F. H.
Ruddy
, and
D. M.
Gilliam
, Eds.,
American Society for Testing and Materials
,
West Conshohoken, PA
,
2001
, pp.
77
84
.
19.
Zaritsky
,
S. M.
,
Vikhrov
,
V. I.
,
Erak
,
D. Y.
,
Kochkin
,
V. N.
,
Brodkin
,
E. B.
, and
Egorov
,
A. L.
, “
Measurement and Calculation of WWER-440 Pressure Vessel Templates Activity for Support of Vessel Dosimetry
,”
ASTM International STP1490
,
West Conshohocken, PA
, May
2008
, pp.
398
407
.
20.
Ballesteros
,
A.
,
Bros
,
J.
,
Debarberis
,
L.
,
Sevini
,
F.
,
Erak
,
D.
,
Gezashchenko
,
S.
,
Kryukov
,
A.
,
Shtrombakh
,
Y.
,
Goloschapov
,
S.
,
Ionov
,
A.
,
Pytkin
,
Y.
,
Anikeev
,
Y.
,
Banyuk
,
G.
,
Plusch
,
A.
,
Gillemot
,
F.
,
Tatar
,
L.
, and
Petrosyan
,
V.
, “
Consolidation of Scientific and Technological Expertise to Assess the Reliability of Reactor Pressure Vessel Embrittlement Prediction in Particular for the Arctic Area Plant (COBRA)
,” NED, Vol.
235
,
2006
, pp.
411
419
.
21.
Serén
,
T.
, “
Completion of the New Surveillance Programme for Loviisa 1. Use of RPV Dosimetry Benchmark’s Results for Determining Radiation Embrittlement Damage
,”
Workshop RADE
,
Bansko
,
Bulgaria
, April 1–8,
2006
.
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