Abstract

To enable the deployment of small modular reactors (SMRs) in Canada, Canadian Nuclear Laboratories (CNL) is interested in the applicability of zero energy deuterium-2 (ZED-2) experiments for validation of Monte Carlo reactor physics codes and models for SMR reactor fuels. This applicability is investigated here by considering potential ZED-2 experiments for testing fuel assemblies (FAs) for two different SMR technologies: the pressurized-water reactor (PWR), and the fluoride-salt-cooled high-temperature reactor (FHR). Each proposed set of mixed-lattice substitution experiments uses driver fuel channels containing CANDU flexible low enriched uranium/recovered uranium (CANFLEX-LEU/RU) fuel bundles. Simulation results indicate that a number of critical core configurations are possible, and should provide suitable reactor physics measurement data that can be used for physics design verification, and also for benchmarking and validation of computational reactor physics codes used in the design, operations, and safety analysis of SMRs based on PWR or FHR technologies.

Issue Section:
Reactor Physics
Topics:
Fuels, Modeling, Physics, Pressurized water reactors, Water, Neutrons, High temperature

References

1.
World Nuclear Association
,
2021
, “
Small Nuclear Power Reactors
,” World Nuclear Association, London, UK, accessed Aug. 19, 2021, https://www.world-nuclear.org/information-library/nuclear-fuel-cycle/nuclear-power-reactors/small-nuclear-power-reactors.aspx
2.
Wojtaszek
,
D.
,
2019
, “
Potential Off-Grid Markets for SMRs in Canada
,”
Can. Nucl. Rev.
,
8
(
2
), pp.
87
–
96
.10.12943/CNR.2017.00007
Google Scholar
Crossref
Search ADS
 
3.
Lee
,
K. W.
,
2020
, “
The Canadian Nuclear Safety Commission's Readiness to Regulate Small Modular Reactors
,”
CNL Nucl. Rev.
,
9
(
1
), pp.
99
–
106
.10.12943/CNR.2019.00005
Google Scholar
Crossref
Search ADS
 
4.
Bromley
,
B. P.
, and
Pencer
,
J.
,
2009
, “
Comparison of MCNP and WIMS-AECL/RFSP Calculations Against Critical Heavy Water Experiments in ZED-2 With CANFLEX-LVRF and CANFLEX-LEU Fuels
,”
Proceedings of M&C
, American Nuclear Society, Saratoga Springs, New York, May 3–7, pp.
597
–
613
.
5.
Canadian Nuclear Laboratories
,
2019
, “
ZED-2 Research Reactor
,” Canadian Nuclear Laboratories, Chalk River, ON, Canada, accessed July 1, 2019, https://web.archive.org/web/20190701213637/http://www.cnl.ca/en/home/facilities-and-expertise/zed-2-research-reactor.aspx
6.
Rauket
,
A. M.
, and
McPhee
,
G. P.
,
2010
, “
Research Activities in the ZED-2 Critical Facility
,”
Proceedings of PHYSOR
, American Nuclear Society, Pittsburgh, PA, May 9–14, pp.
2733
–
2746
.
7.
Bromley
,
B. P.
,
Alexander
,
J.
,
Yan
,
H.
,
Colton
,
A. V.
, and
Golesorkhi
,
S.
,
2019
, “
Physics Assessment of Energy Deposition Distributions in Lattices in PT-HWRs With Uranium and Thorium-Based Fuels
,”
ANS Trans.
,
120
(
1
), pp.
907
–
912
.https://www.ans.org/pubs/transactions/
8.
Colton
,
A. V.
,
Bromley
,
B. P.
,
Wojtaszek
,
D.
, and
Dugal
,
C.
,
2017
, “
Evaluation of Uranium-Based Fuels Augmented by Low Levels of Thorium for Near-Term Implementation in Pressure Tube Heavy Water Reactors
,” Am. Nucl. Soc. (
ANS
) Nucl. Sci. Eng.,
186
(
1
), pp.
48
–
65
.10.1080/00295639.2016.1273021
9.
X-5 Monte Carlo Team
,
2003
, “
MCNP – A General MonteCarlo NParticle Transport Code, Version 5
,” Los Alamos National Laboratory, Los Alamos, NM, Report No. LA-UR-03-1987.
10.
Altiparmakov
,
D. V.
, and
May
,
9-14.
,
2010
, “
ENDF/B-VII.0 Versus ENDF/B-VI.8 in CANDU Calculations
,”
PHYSOR 2010: Advances in Reactor Physics to Power the Nuclear Renaissance
,
American Nuclear Society
,
Pittsburgh, PA
.
11.
Watts
,
D. G.
,
Bromley
,
B. P.
,
Adams
,
F. P.
, and
Zeller
,
M. B.
,
2008
, “
Comparison of MCNP Calculations Against Measurements in Moderator Temperature Experiments With CANFLEX-LEU in ZED-2
,”
Proceedings of 29th Canadian Nuclear Society (CNS) Annual Conference
, June 1–4, Toronto, Paper No.
114
.https://www.researchgate.net/publication/336617352_COMPARISON_OF_MCNP_CALCULATIONS_AGAINST_MEASUREMENTS_IN_MODERATOR_TEMPERATURE_EXPIN_ZED-2
12.
Wong
,
F. C.
,
Bromley
,
B. P.
,
Zeller
,
M. B.
,
Pencer
,
J.
, and
Atfield
,
J.
,
2010
, “
Reactivity and Flux/Calculations Using MCNP for Heavy-Water Experiments in the ZED-2 Critical Facility Using Low-Enriched Uranium Fuel Bundles
,”
Proceedings of PHYSOR 2010
, American Nuclear Society, Pittsburgh, PA, May 9–14, pp.
115
–
124
.https://www.researchgate.net/publication/288426365_Reactivity_and_flux_calculations_using_MCNP_for_heavy-water_experiments_in_the_ZED-2_critical_facility_using_low-enriched_uranium_fuel_bundles
13.
Atfield
,
J. E.
,
Yaraskavitch
,
L. R.
, and
Rand
,
E. T.
,
2018
, “
Kinetics Experiments in ZED-2 Using Heterogeneous Cores of Advanced Nuclear Fuels
,”
Ann. Nucl. Energy
,
121
, pp.
36
–
49
.10.1016/j.anucene.2018.06.035
Google Scholar
Crossref
Search ADS
 
14.
Wilkin
,
G. B.
,
Bromley
,
B. P.
, and
Watts
,
D. G.
,
2012
, “
A Monte Carlo Method for Analyzing Mixed-Lattice Substitution Experiments Using MCNP
,”
AECL/CNL Nucl. Rev.
,
1
(
2
), pp.
33
–
41
.10.12943/ANR.2012.00016
Google Scholar
Crossref
Search ADS
 
15.
Pino-Medina
,
S.
, and
François
,
J.-L.
,
2021
, “
Neutronic Analysis of the NuScale Core Using Accident Tolerant Fuels With Different Coating Materials
,”
Nucl. Eng. Des.
,
377
, p.
111169
.10.1016/j.nucengdes.2021.111169
Google Scholar
Crossref
Search ADS
 
16.
NuScale Power
,
2018
, “
Final Safety Analysis Report (FSAR)—NuScale Standard Plant Design Certification Application—Chapter Four, Reactor, Part 2, Revision 1
,” accessed Aug. 15, 2021, https://www.nrc.gov/docs/ML1701/ML17013A274.pdf
17.
Bergman
,
T. A.
,
2018
, “
Nuclear Analysis Codes and Methods Qualification
,” Revision 1, Docket Number PROJ0769, L0-1118-62438, NuScale Power, LLC Submittal of the Approved Version of NuScale Topical, NuScale Power, Corvallis, OR, No. TR-0616-48793, accessed Aug. 15, 2021, https://www.nrc.gov/docs/ML1823/ML18234A295.pdf
18.
Strasser
,
A.
,
Rudling
,
P.
, and
Patterson
,
C.
,
2014
, “
‘Structure and Components’ Extract From: Fuel Fabrication Process Handbook
,” Revision 1,
Advanced Nuclear Technology International, Mölnlycke
,
Sweden
, accessed Aug. 15, 2021, http://docplayer.net/101038090-Structure-and-components.html
19.
Yan
,
X. L.
,
2016
, “
Very High-Temperature Reactor
,”
Chapter 3, Handbook Generation IV Nuclear Reactors
, Woodhead Publishing, Sawston/Cambridge/England, UK.
20.
Adams
,
F. P.
,
Chow
,
J. C.
,
Bromley
,
B. P.
,
Blomeley
,
L.
, and
Yaraskavitch
,
L.
,
2018
, “
Optimization Studies for Planning of Substitution Experiments in the ZED-2 Critical Facility With Plutonium-Thorium Test Fuel
,”
Ann. Nucl. Energy
,
120
, pp.
742
–
748
.10.1016/j.anucene.2018.06.034
Google Scholar
Crossref
Search ADS
 
21.
Adams
,
F. P.
,
Blomeley
,
L.
, and
Yaraskavitch
,
L.
,
2020
, “
Recent Measurements on Plutonium-Thorium Fuel by Substitution Experiments in the ZED-2 Critical Facility
,”
Ann. Nucl. Energy
,
139
, p.
107281
.10.1016/j.anucene.2019.107281
Google Scholar
Crossref
Search ADS
 
22.
Sharpe
,
J. R.
,
Atfield
,
J. E.
,
Chow
,
J.
,
Yaraskavitch
,
L.
, and
Buijs
,
A.
,
2016
, “
Sensitivity Analysis of ZED-2 Experiments Using (Pu, Th)O2 Fuel Bundles to Assess Their Applicability to the SCWR Conceptual Design
,”
CNL Nucl. Rev.
,
5
(
2
), pp.
299
–
308
.10.12943/CNR.2016.00039
23.
Rearden
,
B. T.
, and
Williams
,
M. L.
,
2007
, “
Overview of the SCALE TSUNAMI Sensitivity and Uncertainty Analysis Tools
,”
Am. Nucl. Soc. Trans.
,
96
(
1
), pp.
535
–
537
.https://www.researchgate.net/publication/228732640_Overview_of_the_SCALE_TSUNAMI_sensitivity_and_uncertainty_analysis_tools
24.
Zhu
,
T.
,
2011
, “
Sensitivity and Uncertainty Analysis of (Th,Pu)O2 Benchmark Experiments in ZED-2 Using TSUNAMI
,” Thesis for Master of Applied Science in Engineering Physics,
McMaster University
, accessed Aug. 15, 2021, https://macsphere.mcmaster.ca/handle/11375/9894
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