Study on transmutation efficiency of the VVER-1000 fuel assembly with different minor actinide compositions
Nuclear Science and Technology, Vol.9, No. 4 (2019), pp. 16-26
Study on transmutation efficiency of the VVER-1000 fuel
assembly with different minor actinide compositions
Tran Vinh Thanh1, Vu Thanh Mai2, Hoang Van Khanh1, Pham Nhu Viet Ha1*
1Institute for Nuclear Science and Technology, Vietnam Atomic Energy Institute,
179 Hoang Quoc Viet str., Cau Giay dist., Hanoi 100000, Viet Nam
2Hanoi University of Science, Vietnam National University,
334 Nguyen Trai, Thanh Xuan, Hanoi 10000, Viet Nam
E-mail*: phamha@vinatom.gov.vn
(Received 06 November 2019, accepted 30 December 2019)
Abstract: The feasibility of transmutation of minor actinides recycled from the spent nuclear fuel in
the VVER-1000 LEU (low enriched uranium) fuel assembly as burnable poison was examined in our
previous study. However, only the minor actinide vector of the VVER-440 spent fuel was considered.
In this paper, various vectors of minor actinides recycled from the spent fuel of VVER-440, PWR-
1000, and VVER-1000 reactors were therefore employed in the analysis in order to investigate the
minor actinide transmutation efficiency of the VVER-1000 fuel assembly with different minor
actinide compositions. The comparative analysis was conducted for the two models of minor actinide
loading in the LEU fuel assembly: homogeneous mixing in the UGD (Uranium-Gadolinium) pins and
coating a thin layer to the UGD pins. The parameters to be analysed and compared include the
reactivity of the LEU fuel assembly versus burnup and the transmutation of minor actinide nuclides
when loading different minor actinide vectors into the LEU fuel assembly.
Keywords: VVER-1000 LEU fuel assembly, burnable poison, minor actinide transmutation.
I. INTRODUCTION
environment, separation and transmutation of
the plutonium and MAs in the used fuel are
esssential [2]. It has been realized that the
transmutation of these actinide into either
short-lived fission products or valued fissile or
stable isotopes can be accomplished in fast
reactors, subcritical reactors or thermal
reactors [1,3-7].
The radioactive waste and spent nuclear
fuel discharged from nuclear power plants
causes a big issue for the countries holding
such nuclear installations. It is widely
recognized that a light water reactor (LWR)
with electric capacity of 1000 MWe, on
average, produces 20-30 metric tonnes of spent
nuclear fuel annually, which consist of
approximately 95 wt% uranium, 1 wt%
plutonium, 4 wt% fission products and minor
actinide (MA) [1]. In the spent fuel, only with
a very small amount of MAs, they still
dominate the decay heat load to the repository
and cumulative long-term radiotoxicity to the
environment. To lessen the burden for disposal
and storage of spent nuclear fuel as well as to
reduce its cumulative radiotoxicity to the
The VVER-1000 reactor (the Russian
Pressurized Water Reactor, PWR) is
nowadays operated in various East
European and Asian countries [8,9]. In
addition to the Western PWRs that have
been extensively studied for their MA
transmutation capabilities [10-14], the
VVER-1000 is also considered as
a
potential candidate for transmutation of
actinide in the spent fuel stock-pile and
©2019 Vietnam Atomic Energy Society and Vietnam Atomic Energy Institute
TRAN VINH THANH et al.
various methods of loading and burning
insignificant change in the reactivity of the fuel
assembly while providing considerable MA
transmutation rates.
transuranic elements in the Western PWRs
may be adopted similarly to the Russian
VVERs. In the past studies, transmuting the
MAs in the burnable poison rods [15,16] or in
some other locations in the PWR fuel
assemblies has been found technically feasible
and recommended as potential transmutation
methods for LWRs, in particular the unique
advantage of loading MAs to partially replace
the excess reactivity control functions of
gadolinium and boric acid.
II. CALCULATION METHOD
The VVER-1000 LEU fuel assembly
specified in the OECD VVER-1000 LEU and
MOX (mixed oxide) Assembly Computational
Benchmark [18] is utilized in the present
investigation to examine the possibility of MA
transmutation as burnable poison in the
VVER-1000 reactor. The configuration of the
LEU fuel assembly are shown in Fig. 1. The
LEU assembly consists of 300 fuel pin cells
with 3.7wt% 235U, 12 UGD pin cells with
3.6wt% 235U and 4wt% Gd2O3, 18 water filled
guide tubes for control insertion and one
central water filled instrumentation tube. The
LEU fuel assembly is modeled by the SRAC
code. The one-sixth of the LEU fuel assembly
modeled by the PIJ module of SRAC is
presented in Fig. 2; the burnup calculations
were performed with the BURN-UP module of
SRAC; and the 107 energy groups based on
the ENDF/B-VII.0 nuclear data library were
used in the SRAC calculations.
In a previous study [17], the feasibility
of MA transmutation in VVER-1000 LEU fuel
assembly [18] as burnable poison was studied
and the results showed that the total MA
transmutation rate of ~20% could be obtained.
However, only the MA vector of the VVER-
440 spent fuel was considered. In the present
work, different MA compositions recycled
from the spent fuels of VVER-440 [4], PWR-
1000 [15] and VVER-1000 [19] with different
burnup levels and cooling time were therefore
employed in the analysis in order to estimate
the effects of various MA contents in the spent
fuel to the infinite multiplication factor (k-inf)
of the VVER-1000 LEU fuel assembly versus
burnup as well as the MA transmutation
efficiency. The SRAC code [20] was used for
modeling of the VVER-1000 LEU fuel
assembly based on the ENDF/B-VII.0 library.
The comparative analysis was conducted for
the two models of MA loading in the LEU fuel
assembly: homogeneous mixing in the UGD
(Uranium-Gadolinium) pins and coating a thin
layer to the UGD pins. The MA loading into
the LEU fuel assembly will be performed
without significant modification of the
assembly configuration to minimize the cost
for fuel fabrication process and respective
changes in reactor core design. The constraint
for these MA loadings is to ensure
In this investigation, we intend to
load the MAs in the UGD pins of the LEU
fuel assembly for their transmutation
without significant change in the fuel
assembly configuration. The purpose is to
investigate the transmutation capability of
the VVER-1000 LEU fuel assembly. To this
end, we consider two approaches to load the
MAs into the fuel assembly while tuning the
gadolinium
content
(1)
and
boron
MAs
concentration:
mixing
homogeneously with UO2 and Gd2O3 in the
UGD pins; and (2) coating a thin layer of
MAs around the UGD pellets. In these
cases, different vectors of MAs were
17
STUDY ON TRANSMUTATION EFFICIENCY OF THE VVER-1000 FUEL ASSEMBLY…
employed including those recycled from the
spent fuel of VVER-440 with 45
GWd/tonne burnup and 5 years of cooling
[4], PWR-1000 with 33 MWd/tonne burnup
and 10 years cooling [15] and VVER-1000
reactors with 40 GWd/tonne burnup and 10
years of cooling [19]. The MA vectors recycled
from the spent fuels of the VVER-440, PWR-
1000 and VVER-1000 are given in Table I. The
parameters to be investigated are the k-inf of the
LEU fuel assembly versus burnup and the MA
transmutation rates in the LEU fuel assembly.
Fig. 1. Configuration of the VVER-1000 LEU fuel assembly
Fig. 2. One-sixth model of the VVER-1000 LEU fuel assembly by SRAC
18
TRAN VINH THANH et al.
Table I. MA vectors used in the analysis
MA vector (Fraction - at.%)
Isotope
237Np 241Am 242mAm 243Am
242Cm
0.001
0.0
243Cm 244Cm 245Cm
246Cm
0.05
0.0
VVER-440 48.89 31.56
PWR-1000 41.80 47.86
0.11
0.0
14.65
0.049
4.43
1.63
2.73
0.26
8.62
0.0
0.09
VVER-1000
0.0
83.75
0.10
13.16 1.22 x 10-6 0.03
0.23 3.59 x 10-6
Additionally, in the case of loading MAs
recycled from spent fuel of VVER-440 reactor,
the excess reactivity was generally higher at
the early burnup steps and became smaller than
the reference case after about 7 MWd/kgHM
as gadolinium burned out.
III. MA TRANSMUTATION IN THE
VVER-1000 FUEL ASSEMBLY
A. Homogeneous mixing of MAs in the
UGD pins
As the MAs are homogeneously mixed
in the UGD pins of the VVER-1000 LEU fuel
assembly, the gadolinium content and boron
concentration were adjusted with varying
content of MAs in order to maintain the
reactivity of the fuel assembly. It is because
the MAs can act as burnable poison and thus
can partially replace the functions of the
gadolinium in the UGD pins and boric acid in
the coolant for excess reactivity control of the
fuel assembly [15,16]. In this calculation, the
content of MAs was loaded up to 10 wt%; the
content of the gadolinium was reduced from
4.0 wt% in the reference case to 2 wt%, 2.5
wt%, 3 wt% and the boron concentration was
reduced correspondingly to compensate the
negative reactivity insertion by the MAs.
The gadolinium content was therefore
increased from 2 to 2.5 wt% to expect a
decrease of the aforementioned high excess
reactivity at the early burnup steps and the
boron concentration was adjusted to 400 ppm
with respect to the MA content of 10 wt%. As
can be seen in Fig. 3, adjusting the gadolinium
content to 2.5 wt% and the boron concentration
to 400 ppm could lead to a comparable cycle
length while still keeping the excess reactivity
somewhat lower than the reference case.
The gadolinium content was further
increased from 2.5 to 3 wt% and the boron
concentration was adjusted to 350 ppm with
respect to the MAs content of 10 wt%. It was
found that the behaviour of the k-inf versus
burnup in these cases is very similar to those
with the gadolinium content of 2.5 wt% as
previously mentioned. However, the cycle
length when loading 10 wt% of MA with the
gadolinium content of 3 wt% and boron
concentration of 350 ppm was further
improved and became almost identical to the
reference case. Moreover, the excess reactivity
of the LEU fuel assembly at the beginning of
the cycle was also further reduced in
comparison to the reference case.
The results of the k-inf of the VVER-
1000 LEU fuel assembly versus burnup were
illustrated in Fig. 3 for cases with MA content
of 10 wt%. The gadolinium content was first
reduced to 2 wt% and the boron concentration
was decreased from 600 ppm (reference case)
to 450 ppm with respect to the MA content of
10 wt%. It was found that the fuel cycle length
when loading 10 wt% of MAs and decreasing
the gadolinium content to 2 wt% and the boron
concentration to 450 ppm was substantially
reduced as compared to the reference case.
19
STUDY ON TRANSMUTATION EFFICIENCY OF THE VVER-1000 FUEL ASSEMBLY…
Fig. 3. The k-inf of the LEU fuel assembly versus burnup when loading 10 wt% of MA and reducing GD to 2
wt% (upper), 2.5 wt% (middle) and 3 wt% (lower)
20
TRAN VINH THANH et al.
Table II. Transmutation capability in case of homogeneous loading 10 wt% of MA
VVER-440 MA vector
PWR-1000 MA vector
VVER-1000 MA vector
Mass reduced
Initial
Mass reduced
after 306 days
Mass reduced
after 306 days
Isotope
Initial
amount
(g)
Initial
amount
(g)
after 306 days
amount
(g)
(g)
(%)
(g)
(%)
(g)
__
(%)
__
237Np
241Am
243Am
244Cm
245Cm
Total
896.78
580.05
269.52
81.54
140.19
15.63
765.09
877.75
158.24
29.94
118.35
15.47
0.00
1536.57
241.75
50.18
223.76
49.80
38.58
18.48
313.70
26.79
35.74
16.93
482.05
38.26
31.37
15.83
-78.84
-93.42
25.86
-42.09
-4.94
-51.62
-103.14
20.02
-28.17
-3.10
-94.09
-187.40
23.33
-39.56
-3.90
4.79
1.65
4.17
1832.67
366.73
1832.67
427.57
1832.67
473.97
The results illustrated in Fig. 3 also
imply that the MAs with the content of up to
10 wt% can be loaded into the VVER-1000
LEU fuel assembly without significantly
affecting the fuel cycle length by means of
reducing the gadolinium content and the
boron concentration to offset the negative
reactivity insertion by the MAs. For the MA
loading up to 10 wt%, it was found that the
lower excess reactivity and equivalent cycle
length as compared to the reference case can
be obtained with the gadolinium content
reduced to around 2.5-3.0 wt% and the boron
concentration reduced to around 350-400
ppm. As a result, loading 10 wt% of MA is
recommended for the sake of excess reactivity
control and high loading amount of MAs
while keeping almost the same cycle length
with the reference case.
length is mostly unaffected when loading with
different MAs vectors.
The transmutation of MA isotopes is
shown in Table II for the cases when loading
10 wt% of MAs and adjusting the gadolinium
content to 3 wt% and the boron concentration
to 350 ppm. It can be seen that the
concentrations of 241Am and 243Am decreased
with fuel burnup while those of 244Cm and
245Cm accumulated with fuel burnup. The
concentration of 237Np decreased with burnup
when loading the VVER-440 and PWR-1000
MA vectors. After 306 days, the 237Np
concentration was reduced ~15.63 % when
loading the VVER-440 MA vector and ~15.47
% when using PWR-1000 MA vector. The
241Am concentration reduced ~38.58 %, ~35.74
% and ~31.37 % while the 243Am concentration
reduced ~18.48 %, ~16.93 % and ~15.83 % in
correspondence with loading VVER-440,
PWR-1000 and VVER-1000 MA vectors.
Meanwhile, those of 244Cm and 245Cm
increased ~51.62%, ~94.09 %, ~78.84 % and
It is found that the case of loading MA
vectors from the VVER-440 shows the highest
k-inf while that from the VVER-1000 exhibits
the lowest k-inf. This also makes the excess
reactivity at the beginning of the cycle when
loading the MA vector from the VVER-440
spent fuel higher than the two others.
However, Fig. 3 indicates that the fuel cycle
~103.14 %, ~187.40 %, ~93.42
%
corresponding to VVER-440, PWR-1000 and
VVER-1000 MA vectors. The results
demonstrate that the transmutation of MAs
21
STUDY ON TRANSMUTATION EFFICIENCY OF THE VVER-1000 FUEL ASSEMBLY…
recycled from spent nuclear fuel in the VVER-
1000 fuel assembly is feasible from neutronic
viewpoint and the total transmutation rate
higher than ~20% can be achieved. Besides, it
is noticed that in case of loading the VVER-
1000 MA vector without 237Np, the transmuted
amount of 241Am was much larger compared
with the two other cases since the initial
Fig. 4. Coating a thin layer of MA to the UGD pellet
loading amount of this isotope was more than
two times larger. This explained why the case
of loading the VVER-1000 MA vector
exhibited the highest total MA transmutatiton
mass and efficiency as can be found in Table
II. It is also worth noting that more than 90%
of the radiotoxidity of MAs from long time
storage spent fuel (more than hundred years)
come from 241Am (half-life of 432 years).
Thus, with the significant amount of 241Am
that was transmuted in the VVER-1000 fuel
assembly, it could contribute to a significant
reduction of radiotoxicity level of the
radioactive waste.
The results of the k-inf of the VVER-
1000 LEU assembly versus burnup when
coating MAs to the UGD pins and reducing
the gadolinium content and boron
concentration are shown in Fig. 5 in relation
to the reference case. It was found that the
cases of reducing only the gadolinium
content led to a significantly lower excess
reactivity at the beginning of the cycle and
a considerably shorter cycle length. This
behavior of the k-inf versus burnup is
similar to the cases of homogeneous loading
as above mentioned. For that reason, the
boron concentration was reduced to 400
ppm, 350 ppm, and 300 ppm with respect to
the gadolinium content of 2 wt%, 2.5 wt%,
and 3 wt%. It is worth noting that the
amount of boron concentration reduction in
these cases was about 50 ppm larger than
the respective ones of homogeneous loading
due to the self-shielding effect of MAs. The
excess reactivity at the early burnup steps
when reducing the gadolinium content to 2
wt%, 2.5 wt%, and 3 wt% was generally
lower than the reference case; except that it
was slightly higher for the case of the VVER-
440 MA vector with the gadolinium content
of 2 and 2.5 wt% (Fig. 5). Sooner or later the
k-inf in the three cases became smaller than
the reference case. However, the cycle length
with gadolinium content of 2.5 and 3 wt%
was almost the same with the reference case
while that with gadolinium content of 2 wt%
was somewhat shorter. Consequently,
B. Coating a thin layer of MAs to the
UGD pins
In the case of heterogeneous loading of
MAs in the UGD pins of the VVER-1000 LEU
fuel assembly, MAs were coated as a thin layer
at the outside of the UGD pellets as shown in
Fig. 4. The thickness of the cladding was kept
unchanged and the outer radius of the UGD
region was reduced to accommodate the layer
of MAs. For the purpose of MA burning and
keeping the fuel cycle length, the MA content
of 10 wt% was selected in this investigation.
The MA coated layer (see Fig. 4) equivalent to
homogeneous loading with 10 wt% of MA is
0.01981 cm thick. Similar to the case of
homogeneous mixing, the gadolinium content
and boron concentration were also reduced to
compensate the negative reactivity insertion by
the MAs.
22
TRAN VINH THANH et al.
reducing the gadolinium content to 3 wt% and
homogeneous and heterogeneous loadings was
relatively small. However, the transmutation
mass in the case of heterogeneous loading was
slightly higher than that with homogeneous
loading, in particular for the case of VVER-
440 MA vector. Table III also signify that the
highest total MA transmutation mass and
efficiency was again achieved for the case of
loading the VVER-1000 MA vector as
compared to the two other cases.
boron concentration to 300 ppm is
recommended when coating with 10 wt% of
MA to the UGD pellets. The transmutation of
MA isotopes when coating with 10 wt% of
MAs and reducing the gadolinium content to
3 wt% and boron concentration to 300 ppm is
given in Table III. Comparing Tables III and
II, it is shown that the difference in the
transmutation rate of MA isotopes between
Fig. 5. The k-inf of the LEU fuel assembly versus burnup when coating a layer of MAs to the UGD pins and
reducing GD to 2 wt% (upper), 2.5 wt% (middle) and 3 wt% (lower)
23
STUDY ON TRANSMUTATION EFFICIENCY OF THE VVER-1000 FUEL ASSEMBLY…
Table III. Transmutation capability in case of heterogeneous loading of 10 wt% MA
VVER-440 MA vector
PWR-1000 MA vector
VVER-1000 MA vector
Mass reduced
Initial
Mass reduced
after 306 days
Mass reduced
after 306 days
Isotope
Initial
amount
(g)
Initial
amount
(g)
after 306 days
amount
(g)
(g)
(%)
(g)
(%)
(g)
__
(%)
__
237Np
241Am
243Am
244Cm
245Cm
Total
896.79
580.05
269.51
81.53
150.40
16.77
766.06
877.12
157.98
29.87
118.35
15.45
0.00
1536.83
241.56
50.12
238.34
51.13
41.09
18.97
317.87
24.03
36.24
15.21
494.08
34.39
32.15
14.23
-41.27
-7.81
-50.62
-142.27
21.38
-25.87
-3.44
-86.61
-208.80
23.51
-36.42
-4.85
-72.67
-116.46
26.43
4.79
1.65
4.17
1832.67
391.79
1832.67
430.93
1832.67
484.39
level of the radioactive waste since more
than 90% of the radiotoxidity of MAs from
long time storage spent fuel (more than
hundred years) come from 241Am (half-life
of 432 years). Furthermore, the case of
loading the VVER-1000 MA vector is
highly recommended as it could lead to the
highest 241Am transmutation mass as well as
the highest total MA transmutation mass
and efficiency.
IV. CONCLUSIONS
In this study, the efficiency of MA
transmutation as burnable poison in the
VVER-1000 LEU fuel assembly was
examined using the SRAC code for the MA
homogeneous and heterogeneous loading
parterns with different vectors of MAs
recycled from the spent fuel of VVER-440,
PWR-1000, and VVER-1000 reactors. The
gadolinium content
and
the boron
In addition, it was shown that the MAs
loading in combination with the reduction in
gadolinium and boron concentration could help
facilitate the excess reactivity control at the
beginning of the fuel cycle without significant
effect on the cycle length. Moreover, the MA
coating approach could increase slightly the
MA burning efficiency when comparing with
homogeneous MA mixing model because of
the self shielding effect on MAs, especially for
the VVER-440 MA vector. Besides, the results
indicate that, although loading of different MA
vectors slightly affected the fuel cycle length,
loading the MA vectors with lower amount of
237Np and higher amount of 241Am could help
significantly reduce the excess reactivity at the
beginning of the cycle.
concentration were reduced correspondingly
to compensate the negative reactivity
insertion by MA loading. The results show
that, with 10 wt% of MAs loading, 2.5-3.0
wt% of gadolinium content and 400-350 ppm
of boron concentration were recommended
for homogeneous mixing MAs in the UGD
pins while 3 wt% of gadolinium content and
300 ppm of boron concentration were
recommended for heterogeneous loading of
MAs in the UGD pins. It was also found that
237Np, 241Am, and 243Am could be
significantly transmuted with a transmutation
rate as high as ~40% for 241Am. With this
transmutation capability, burning MAs in the
VVER-1000 fuel assembly could contribute
to a significant reduction of radiotoxicity
24
TRAN VINH THANH et al.
reactivity swings,” Nuclear Technology, vol.
Further investigation on transmutation
of MAs and radiotoxicity reduction at a full
core level and MOX core of the VVER-1000
reactor is being planned.
205, no. 11, pp. 1460–1473, 2019.
[8]. Vladimir Sebian, Vladimir Necas, Petr Darilek,
Transmutation of spent fuel in reactor VVER-
440, Journal of Electrical Engineering, Vol. 52,
No. 9-10, 299-302, 2001.
ACKNOWLEDGMENTS
[9]. B. R. Bergelson, A. S. Gerasimov, G. V.
Tikhomirov, Transmutation of actinide in
This research is funded by Vietnam
National Foundation for Science and
Technology Development (NAFOSTED)
under grant number 103.99-2018.32.
power
reactors,
Radiation
Protection
Dosimetry, Vol. 116, No. 1–4, pp. 675–678,
2005, doi:10.1093/rpd/nci249.
[10]. Eugene Shwageraus, Pavel Hejzlar, Mujid S.
Kazimi, A combined nonfertile and UO2 PWR
fuel assembly for actinide waste minimization,
Nuclear Technology, Vol. 149, March 2005.
REFERENCES
[1]. OECD/NEA, Minor Actinide Burning in
Thermal Reactors, Nuclear Energy Agency,
NEA No. 6997, 2013.
[11]. T. A. Taiwo, T. K. Kim, J. A. Stillman, R. N.
Hill, M. Salvatores, P. J. Finck, Assessment of
a heterogeneous PWR assembly for plutonium
and minor actinide recycle, Nuclear
Technology, Vol. 155, July 2006.
[2]. Robert Jubin, Spent Fuel Reprocessing,
Introduction to Nuclear Chemistry and Fuel
Cycle Separations Course, Consortium for Risk
Evaluation with Stakeholder Participation,
ourse/, 2008.
[12].Michael A. Pope, R. Sonat Sen, Abderrafi M.
Ougouag, Gilles Youinou, Brian Boer, Neutronic
analysis of the burning of transuranics in fully
ceramic micro-encapsulated tri-isotropic particle-
fuel in a PWR, Nuclear Engineering and Design
[3]. C.H.M. Broeders, E. Kiefhaber, H.W. Wiese,
Burning transuranium isotopes in thermal and
fast reactors, Nuclear Engineering and Design
202, 157–172, 2000.
252,
215–
225,
2012,
[4]. Z. Perkó, J. L. Kloosterman, S. Fehér, Minor
actinide transmutation in GFR600, Nuclear
Technology, Vol. 177, No. 1, pp. 83-97,
January 2012.
[13]. Bin Liu, Kai Wang, Jing Tu, Fang Liu, Liming
Huang, Wenchao Hua, Transmutation of minor
actinide in the pressurized water reactors, Annals
of Nuclear Energy 64 (2014) 86–92,
[5]. Timothée Kooyman, Laurent Buiron, Gérald
Rimpault, A comparison of curium, neptunium
and americium transmutation feasibility, Annals
of Nuclear Energy 112 (2018) 748–758,
[14]. Bin Liu, Rendong Jia, Ran Han, Xuefeng Lyu,
Jinsheng Han, Wenqiang Li, Minor actinide
transmutation characteristics in AP1000, Annals
of Nuclear Energy 115 (2018) 116–125,
[6]. H. N. Tran, Y. Kato, New 237Np burning strategy
in a supercritical CO2-cooled fast reactor core
attaining zero burnup reactivity loss, Nuclear
Science Engineering 159, 83-93, 2008.
[15]. Wenchao Hu, Bin Liu, Xiaoping Ouyang, Jing
Tu, Fang Liu, Liming Huang, Juan Fu, Haiyan
Meng, Minor actinide transmutation on PWR
burnable poison rods, Annals of Nuclear
[7]. H. N. Tran, Y. Kato, P. H. Liem, V. K. Hoang,
and S. M. T. Hoang, “Minor actinide
transmutation in supercritical-CO2-cooled and
sodium-cooled fast reactors with low burnup
Energy
77
(2015)
74–82,
25
STUDY ON TRANSMUTATION EFFICIENCY OF THE VVER-1000 FUEL ASSEMBLY…
[16]. Wenchao Hu, Jianping Jing, Jinsheng Bi,
Chuanqi Zhao, Bin Liu, Xiaoping Ouyang,
Minor actinide transmutation on pressurized
water reactor burnable poison rods, Annals of
Nuclear Energy 110 (2017) 222–229,
[19]. OECD/NEA, A VVER-1000 LEU and MOX
Assembly Computational Benchmark, Nuclear
Energy Agency, NEA/NSC/DOC 10, 2002.
[20]. A. Kotchetkov, I. Krivitskiy, N. Rabotnov, A.
Tsiboulia, S. Iougai, Calculation and
experimental studies on minor actinide reactor
[17]. V. T. Tran et al., Study on Transmutation of
Minor Actinides as Burnable Poison in VVER-
1000 Fuel, Science and Technology of Nuclear
Installations, Volume 2019, Article ID
5769147, 2019.
transmutation,
Proceedings
of
Fifth
OECD/NEA Information Exchange Meeting
on Actinide and Fission Product Partitioning
and Transmutation, pp. 289-303, Mol,
Belgium, 25-27 November 1998.
[18].OECD/NEA, A VVER-1000 LEU and
[21]. K. Okumura, T. Kugo, K. Kaneko, and K.
Tsuchihashi, SRAC2006: A Comprehensive
Neutronics Calculation Code System, JAEA-
Data/Code 2007-004, 2007.
MOX
Assembly
Computational
Benchmark, Nuclear Energy Agency,
NEA/NSC/DOC 10, 2002.
26
11 trang
2860
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