Abstract
The feasibility of transuranic (TRU) fuel rods has been studied for a dual-cooled VVER-1000 assembly along with the conventional UO2 fuel rods. It has been found that the heterogeneous arrangements of TRU and UO2 fuel rods help to improve the multiplication factor, enhance the fuel cycle parameters, and maintain the negative Doppler coefficient of the reference VVER-1000 assembly. Within the different heterogeneous combinations of TRU and UO2 fuel rods, the equal number of UO2 and TRU fuel rods, which is referred to as model 6 increased the multiplication factor of the reference assembly by 7.66% at the beginning of the cycle. Furthermore, the fuel cycle parameter becomes almost double for this model in comparison with the reference assembly. TRU rods make the neutron spectrum of reference assembly slightly harder and increase the fast fission rate. However, the Doppler coefficient becomes less negative, and flux level decreases with increasing the number of TRU rods. By considering the safety parameters and neutronic behavior, model 6 (equal number of UO2 and TRU fuel rods) is to be effective for the annular fueled VVER-1000 reactor.
Issue Section:
Nuclear Fuels/Cycles and Materials
Topics:
Cycles,
Fuel rods,
Fuels,
Manufacturing,
Neutron flux,
Neutrons,
Nuclear fission,
Nuclear fuel cycle,
Rods,
Safety
References
1.
Fanghänel
,
T.
,
Glatz
,
J. P.
,
Konings
,
R. J. M.
,
Rondinella
,
V. V.
, and
Somers
,
J.
, 2010
, “
Transuranium Elements in Nuclear Fuel Cycle
,” Handbook of Nuclear Engineering, Volume 1, Nuclear Engineering Fundamentals
,
D. G.
Cacuci
, ed.,
Springer
,
Boston, MA
, pp. 2937
–2998
.2.
Morreale
,
A. C.
,
Ball
,
M. R.
,
Novog
,
D. R.
, and
Luxat
,
J. C.
, 2012
, “
The Behaviour of Transuranic Mixed Oxide Fuel in a CANDU-900 Reactor
,” International Conference on the Physics of Reactors, PHYSOR 2012: Advances in Reactor Physics
, Knoxville, TN, Apr. 15–20, pp. 1710
–1725
.https://www.researchgate.net/publication/283402166_The_behaviour_of_transuranic_mixed_oxide_fuel_in_a_Candu-900_reactor3.
Dsouza
,
B.
, 2015
, “
Neutronic Analysis of Light Water Small Modular Reactor With Flexible Fuel Configurations
,” Master's thesis,
Missouri University of Science and Technology
, Rolla, MO.4.
Necas
,
V.
,
Sebian
,
V.
,
Kociskova
,
K.
, and
Darilek
,
P.
, 2005
, “Radiotoxicity and Risk Reduction of TRU Elements From Spent Fuel by Transmutation in the Light Water Reactor,” AIP Conf. Proc., 769, pp. 1474
–1477
.10.1063/1.19452835.
Nakajima
,
K.
, ed., 2015
, “
Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core
,” Nuclear Back-End and Transmutation Technology for Waste Disposal
,
Springer
, Tokyo, pp. 155
–167
.10.1007/978-4-431-55111-9_156.
Hwang
,
D. H.
, and
Hong
,
S. G.
, 2022
, “
Neutronic Analysis on TRU Multi-Recycling in PWR-Based SMR Core Loaded With MOX (U-TRU) and FCM (TRU) Fueled Assemblies
,” Ann. Nucl. Energy
,
179
, p. 109435
.10.1016/j.anucene.2022.1094357.
Guzman
,
J. R.
,
Espinosa-Paredes
,
G.
,
François
,
J. L.
, and
Martín-del-Campo
,
C.
, 2010
, “
A Novel Method for Transuranic Fuel Design
,” Prog. Nucl. Energy
,
52
(7
), pp. 689
–697
.10.1016/j.pnucene.2010.03.0038.
Lindley
,
B. A.
,
Franceschini
,
F.
, and
Parks
,
G. T.
, 2014
, “
The Closed Thorium-Transuranic Fuel Cycle in Reduced-Moderation PWRs and BWRs
,” Ann. Nucl. Energy
,
63
, pp. 241
–254
.10.1016/j.anucene.2013.07.0529.
Fiorina
,
C.
,
Stauff
,
N.
,
Franceschini
,
F.
,
Wenner
,
M.
,
Stanculescu
,
A.
,
Kim
,
T.
,
Cammi
,
A.
,
Ricotti
,
M. E.
,
Hill
,
R.
,
Taiwo
,
T.
, and
Salvatores
,
M.
, 2013
, “
Comparative Analysis of Thorium and Uranium Fuel for Transuranic Recycle in a Sodium Cooled Fast Reactor
,” Ann. Nucl. Energy
,
62
, pp. 26
–39
.10.1016/j.anucene.2013.06.00110.
Nia
,
A. E.
,
Faghihi
,
F.
, and
Hadad
,
K.
, 2012
, “
Prompt and Power Reactivity Coefficients for the Next Generation VVER-1000 Reactor Including Hexagonal Assemblies and Annular Fuels
,” Prog. Nucl. Energy
,
61
, pp. 41
–47
.10.1016/j.pnucene.2012.05.01011.
Mozafari
,
M. A.
, and
Faghihi
,
F.
, 2013
, “
Design of Annular Fuels for a Typical VVER-1000 Core: Neutronic Investigation, Pitch Optimization, and MDNBR Calculation
,” Ann. Nucl. Energy
,
60
, pp. 226
–234
.10.1016/j.anucene.2013.04.03512.
Faghihi
,
F.
, and
Mirvakili
,
S. M.
, 2011
, “
Shut-Down Margin Study for the Next Generation VVER-1000 Reactor Including 13 × 13 Hexagonal Annular Assemblies
,” Ann. Nucl. Energy
,
38
(11
), pp. 2533
–2540
.10.1016/j.anucene.2011.07.00813.
Ahmed
,
M. T.
,
Sahadath
,
M. H.
, and
Islam
,
M. A.
, 2023
, “
Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000
,” ASME J. Nucl. Eng. Radiat. Sci.
,
9
(3
), p. 11
.10.1115/1.405552214.
Ahmed
,
M. T.
, and
Shelley
,
A.
,
2023
, “
Annular Fuel for VVER-1000 Reactor: Moderation Impact on Neutronic Behavior
,” Prog. Nucl. Energy
,
165
, pp. 104907
10.1016/j.pnucene.2023.10490715.
Yuan
,
Y.
, 2004
, “The Design of High-Power Density Annular Fuel for LWRs,” Ph.D. thesis, Department of Nuclear Engineering,
Massachusetts Institute of Technology
,
Cambridge, MA
.16.
Hejzlar
,
P.
, and
Kazimi
,
M. S.
, 2007
, “
Annular Fuel for High-Power-Density Pressurized Water Reactors: Motivation and Overview
,” Nucl. Technol.
,
160
(1
), pp. 2
–15
.10.13182/NT160-2-1517.
Tran
,
H. N.
,
Hoang
,
V. K.
,
Liem
,
P. H.
, and
Hoang
,
H. T.
, 2019
, “
Neutronics Design of VVER-1000 Fuel Assembly With Burnable Poison Particles
,” Nucl. Eng. Technol.
,
51
(7
), pp. 1729
–1737
.10.1016/j.net.2019.05.02618.
Romano
,
P. K.
,
Horelik
,
N. E.
,
Herman
,
B. R.
,
Nelson
,
A. G.
,
Forget
,
B.
, and
Smith
,
K.
, 2015
, “
OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development
,” Ann. Nucl. Energy
,
82
, pp. 90
–97
.10.1016/j.anucene.2014.07.04819.
Burns
,
J. R.
,
Hernandez
,
R.
,
Terrani
,
K. A.
,
Nelson
,
A. T.
, and
Brown
,
N. R.
, 2020
, “
Reactor and Fuel Cycle Performance of Light Water Reactor Fuel With 235 U Enrichment Above 5%
,” Ann. Nucl. Energy
,
142
, p. 107423
.10.1016/j.anucene.2020.10742320.
Rokhmadi
,
R. K. D.
,
Suwoto
,
S. W.
, and
Zuhair
,
Z. H.
, 2016
, “
Analysis of Doppler Reactivity Coefficient on the Typical PWR-1000 Reactor With MOX Fuel
,” KnE Energy
, vol. 2016.10.18502/ken.v1i1.47321.
Pandey
,
Y. K.
, and
Chauhan
,
A.
, 2007
, “Fuel Management of WWER-1000 Reactors of Kudankulam Nuclear Power Plant, India,” International Conference on WWER Fuel Performance, Modelling and Experimental Support, Albena, Bulgaria, Sept. 17
–21
.Copyright © 2024 by ASME
You do not currently have access to this content.
