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ASTM Selected Technical Papers
Reactor Dosimetry: 16th International Symposium
By
Mary Helen Sparks
Mary Helen Sparks
Symposium Chairperson and STP Editor
1
White Sands Missile Range
,
White Sands, NM,
US
Search for other works by this author on:
K. Russell DePriest
K. Russell DePriest
Symposium Chairperson and STP Editor
2
Sandia National Laboratories
,
Albuquerque, NM,
US
Search for other works by this author on:
David W. Vehar
David W. Vehar
Symposium Chairperson and STP Editor
3
Sandia National Laboratories
,
Albuquerque, NM,
US
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ISBN:
978-0-8031-7661-4
No. of Pages:
654
Publisher:
ASTM International
Publication date:
2018

The fast neutron fluence and the corresponding uncertainty are important parameters for reactor pressure vessel lifetime. This article presents one model, under development at CEA (Commissariat à l’Energie Atomique et aux Energies Alternatives), that uses the deterministic code APOLLO3® for uncertainty calculations of the fast fluence for pressurized water reactor irradiation surveillance. All calculations are made by MINARET, a 3D-SN solver of the APOLLO3® code that uses the discontinuous Galerkin finite elements approximation. The spatial mesh is unstructured, and the transport calculations are parallelized with respect to the angular directions. In this numerical scheme, the multigroup cross sections are sub-group self-shielded and collapsed over a dedicated energy mesh optimized by the adaptive energy mesh constructor. Results from this model are encouraging with respect to the Monte Carlo reference TRIPOLI-4®. The integral of the flux over 1 MeV in the locations of interest (surveillance capsule and vessel) is calculated in less than 20 min with an error lower than 1 %. Some examples of uncertainty calculations associated with design parameters in which the MINARET solver is coupled to the CEA uncertainty and sensitivity platform URANIE are also provided.

1.
Schneider
,
D.
,
Dolci
,
F.
,
Gabriel
,
F.
,
Palau
,
J-M.
,
Guillo
,
M.
,
Pothet
,
B.
,
Archier
,
P.
, et al
APOLLO3®: CEA/DEN Deterministic Multi-Purpose Code for Reactor Physics Analysis
,” presented at
PHYSOR-2016
,
Sun Valley, ID
, May 1–5,
2016
.
2.
Lautard
,
J-J.
and
Moller
,
J-Y.
, “
MINARET, a Deterministic Neutron Transport Solver for Nuclear Core Calculations
,” presented at
M&C 2011
,
Rio de Janeiro, Brazil
, May 8-12
2011
.
3.
Mosca
,
P.
,
Mounier
,
C.
,
Sanchez
,
R.
, and
Arnaud
,
G.
, “
An Adaptive Energy Mesh Constructor for Multigroup Library Generation for Transport Codes
,”
Nucl. Sci. Eng.
, Vol.
167
, No.
1
,
2011
, pp. 40–60.
4.
Nuclear Energy Agency
, “
TRIPOLI-4 Version 8.1, 3D General Purpose Continuous Energy Monte Carlo Transport Code
,” NEA-1716 TRIPOLI-4 Version 8.1, http://web.archive.org/web/20180620152741/https://www.oecd-nea.org/tools/abstract/detail/nea-1716 (accessed June 20, 2018).
5.
Gaudier
,
F.
, “
URANIE: The CEA/DEN Uncertainty and Sensitivity Platform
,”
Procedia Soc. Behav. Sci.
, Vol.
2
, No.
6
,
2010
, pp. 7660–7661.
6.
Mosca
,
P.
,
Mounier
,
C.
,
Bellier
,
P.
, and
Zmijarevic
,
I.
, “
Improvements in Transport Calculations by the Energy-Dependent Fission Spectra and Subgroup Method for Mutual Shielding
,”
Nucl. Sci. Eng.
, Vol.
175
, No.
3
,
2013
, pp. 266–282.
7.
Sanchez
,
R.
,
Zmijarevi
,
I.
,
Coste-Delclaux
,
M.
,
Masiello
,
E.
,
Santandrea
,
S.
,
Martinolli
,
E.
,
Villate
,
L.
,
Schwartz
,
N.
, and
Guler
,
N.
, “
APOLLO2 Years 2010
,”
Nucl. Eng. Technol.
, Vol.
42
, No.
5
,
2010
, pp. 474–499.
8.
Mosca
,
P.
,
Taofiki
,
A.
,
Bellier
,
P.
, and
Prévost
,
A.
, “
Energy Mesh Optimization for Multi-Level Calculation Schemes
,” presented at the
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011)
,
Rio de Janeiro, Brazil
, May 8–12,
2011
.
9.
Kodeli
,
I.
, “
Multidimensional Deterministic Nuclear Data Sensitivity and Uncertainty Code System: Method and Application
,”
Nucl. Sci. Eng.
, Vol.
138
, No.
1
,
2001
, pp. 45–66.
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