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ASTM Selected Technical Papers
Reactor Dosimetry: 14th International Symposium
By
David W. Vehar
David W. Vehar
JAI Guest Editor
1
Sandia National Laboratories
,
Albuquerque, New Mexico,
US
Search for other works by this author on:
Douglas L. Selby
Douglas L. Selby
JAI Guest Editor
2
Oak Ridge National Laboratory
,
Oak Ridge, TN,
US
Search for other works by this author on:
Mary Helen Sparks
Mary Helen Sparks
JAI Guest Editor
3
White Sands Missile Range
,
White Sands, NM,
US
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ISBN:
978-0-8031-7536-5
No. of Pages:
794
Publisher:
ASTM International
Publication date:
2012

The approach of improved uncertainty-accounted conservative evaluation of vodo-vodyanoi energetichesky reactor (VVER) (reactor-) pressure-vessel (RPV) radiation loading parameters has been proposed. This approach is based on the calculational–experimental procedure, which takes into account C/E ratio, depending on over- or underestimation, and uncertainties of measured and calculated results. An application of elaborated approach to the full-scale ex-vessel neutron dosimetry experiments on Russian VVERs combined with neutron-transport calculations has been demonstrated in the paper.

1.
Recording of Fast Neutron Fluence at VVER Pressure Vessels and Surveillance Specimens for Ulterior Prediction of RPV Radiation Lifetime
,”
RB-007-99 Bull. GOSATOMNADZOR Russ.
, Vol.
3
, No.
5
,
1999
, pp. 2–14 (in Russian).
2.
State System for Ensuring the Uniformity of Measurement. Recommendation for Radiation Monitoring Procedures. Common Requirements
,” MI 2453-2000, VNIIFTRI, 2000 (in Russian).
3.
Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence
,”
U.S. Nuclear Regulatory Commission, Regulatory Guide
, Vol.
1
,
2001
, p. 190.
4.
Rhoades
,
W.
and
Childs
,
R.
, “
TORT/DORT: Two- and Three Dimensional Discrete Ordinates Transport
,” CCC-543, RSIC, ORNL, TN,
1991
.
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White
,
J. E.
,
Ingersoll
,
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,
Wright
,
R. Q.
,
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,
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,
Slater
,
C. O.
,
Greene
,
N. M.
,
MacFarlane
,
R. E.
,
Roussin
,
R. W.
, “
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 Collection, DLC-185, March
1996
.
6.
Osmera
,
B.
and
Zaritsky
,
S.
, Proc. of 11th ISRD, pp. 689–696.
7.
Maerker
,
R. E.
,
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,
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, and
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,
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,
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, Vol.
91
,
1985
, p. 369.
8.
Borodkin
,
G.
,
Khrennikov
,
N.
,
Gordon
,
B.
,
Borodkin
,
P.
,
Miroshnichenko
,
M.
, “
Monitoring of Radiation Load of Pressure Vessels of Russian VVER in Compliance with License Amendments
,”
Proc. of the 13th International Symposium on Reactor Dosimetry State of the Art 2008
, May 25–29, 2008,
Akersloot, the Netherlands
,
Voorbraak
W.
,
Debarberis
L.
,
D'hondt
P.
,
Wagemans
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, eds.,
World Scientific
,
Singapore
,
2008
, pp. 404–411.
9.
Borodkin
,
P.
,
Borodkin
,
G.
,
Khrennikov
,
N.
, and
Konheiser
,
J.
, “
Application of Ex-Vessel Neutron Dosimetry Combined with in-Core Measurements for Correction of Neutron Source Used for RPV Fluence Calculations
,” Paper for 14-th ISRD, 2011, to be published by J. ASTM Int.,
2012
.
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