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Home > Publishers > AIP Publishing > AIP Conference Proceedings > Conference Proceeding
INTERNATIONAL CONFERENCE ON PHYSICS AND ITS
APPLICATIONS: (ICPAP 2011)
Conference date: 10–11 November 2011
Location: Bandung, Indonesia
ISBN: 978-0-7354-1055-8
Editors: Khairul Basar and Sparisoma Viridi
Volume number: 1454
Published: 20 June 2012
Front Matter
Source: AIP Conf. Proc. 1454 (2012); http://dx.doi.org/10.1063/v1454.frontmatter
VIEW DESCRIPTIO N
Preface: International Conference on Physics and Its Applications (ICPAP 2011)
Khairul Basar and Sparisoma Viridi
Source: AIP Conf. Proc. 1454, 1 (2012); http://dx.doi.org/10.1063/1.4730673
VIEW DESCRIPTIO N
INVITED PAPERS
Direct observation of local chemical surface properties by scanning tunneling microscopy
Harry E. Hoster
Source: AIP Conf. Proc. 1454, 9 (2012); http://dx.doi.org/10.1063/1.4730676
VIEW DESCRIPTIO N
Accurate force measurement using optical interferometer
Yusaku Fujii
Source: AIP Conf. Proc. 1454, 15 (2012); http://dx.doi.org/10.1063/1.4730677
VIEW DESCRIPTIO N
Appropriate observables for investigating narrow resonances in kaon photoproduction off a
proton
T. Mart
Source: AIP Conf. Proc. 1454, 19 (2012); http://dx.doi.org/10.1063/1.4730678
VIEW DESCRIPTIO N
ASTROPHYSICS AND HIGH ENERGY PHYSICS
The characteristics of solar wind parameters during minimum periods of solar cycle 24 and
impact on geoeffectiveness
Dhani Herdiwijaya
Source: AIP Conf. Proc. 1454, 25 (2012); http://dx.doi.org/10.1063/1.4730679
VIEW DESCRIPTIO N
Morning twilight measured at Bandung and Jombang
Eka Puspita Arumaningtyas, Moedji Raharto and Dhani Herdiwijaya
Source: AIP Conf. Proc. 1454, 29 (2012); http://dx.doi.org/10.1063/1.4730680
VIEW DESCRIPTIO N
The surface distribution of solar energetic particles on the Earth and Southern Atlantic
Anomaly
Febi Trihermanto and Dhani Herdiwijaya
Source: AIP Conf. Proc. 1454, 32 (2012); http://dx.doi.org/10.1063/1.4730681
VIEW DESCRIPTIO N
The possible range arc of vision for Aphelion and Perihelion group of Hilal visibility
Moedji Raharto and Novi Sopwan
Source: AIP Conf. Proc. 1454, 35 (2012); http://dx.doi.org/10.1063/1.4730682
VIEW DESCRIPTIO N
Population density effect on radio frequencies interference (RFI) in radio astronomy
Roslan Umar, Zamri Zainal Abidin, Zainol Abidin Ibrahim, Mohd Saiful Rizal Hassan, Zulfazli Rosli and Zety
Shahrizat Hamidi
Source: AIP Conf. Proc. 1454, 39 (2012); http://dx.doi.org/10.1063/1.4730683
VIEW DESCRIPTIO N
Indication of radio frequency interference (RFI) sources for solar burst monitoring in Malaysia
Z. S. Hamidi, Z. Z. Abidin, Z. A. Ibrahim and N. N. M. Shariff
Source: AIP Conf. Proc. 1454, 43 (2012); http://dx.doi.org/10.1063/1.4730684
VIEW DESCRIPTIO N
Nonminimal derivative coupling in five dimensional universal extra dimensions and recovering
the cosmological constant
Agus Suroso, Freddy P. Zen and Bobby E. Gunara
Source: AIP Conf. Proc. 1454, 47 (2012); http://dx.doi.org/10.1063/1.4730685
VIEW DESCRIPTIO N
NUCLEAR PHYSICS AND APPLICATIONS
The assessment of consistency using penetrometer and apparent diffusion coefficient (ADC)
value using diffusion weighted magnetic resonance imaging (DW-MRI) from polyvinyl alcohol
(PVA) formed by freezing-thawing cycle
Yanurita Dwihapsari, Dita Puspita Sari and Darminto
Source: AIP Conf. Proc. 1454, 53 (2012); http://dx.doi.org/10.1063/1.4730686
VIEW DESCRIPTIO N
Determination of Cu, Zn and Pb in scalp hair from a selected population in Penang using the
XRF method
Khalid Saleh Ali Aldroobi, A. Shukri, Eid Mahmoud Eid Abdel Munem, Sabar Bauk, Mohammad Wasef
Marashdeh and Yahye Abbas Amin
Source: AIP Conf. Proc. 1454, 57 (2012); http://dx.doi.org/10.1063/1.4730687
VIEW DESCRIPTIO N
Impact of curved surface for clinical plan verification in intensity modulated radiation therapy
using 2d array I'mRT MatriXX
Saleh Alashraha, Sivamany Kandaiya and Soon Keong Cheng
Source: AIP Conf. Proc. 1454, 61 (2012); http://dx.doi.org/10.1063/1.4730688
VIEW DESCRIPTIO N
Computational study: Reduction of iron corrosion in lead coolant of fast nuclear reactor
Artoto Arkundato, Zaki Su’ud, Mikrajuddin Abdullah and Widayani
Source: AIP Conf. Proc. 1454, 65 (2012); http://dx.doi.org/10.1063/1.4730689
VIEW DESCRIPTIO N
Design of small gas cooled fast reactor with two region of natural Uranium fuel fraction
Menik Ariani, Zaki Su’ud, Abdul Waris, Khairurrijal, Fiber Monado, Hiroshi Sekimoto and Sinsuke Nakayama
Source: AIP Conf. Proc. 1454, 69 (2012); http://dx.doi.org/10.1063/1.4730690
VIEW DESCRIPTIO N
Preliminary study on direct recycling of spent BWR fuel in BWR system
A. Waris, Sumbono, Dythia Prayudhatama, Novitrian and Zaki Su’ud
Source: AIP Conf. Proc. 1454, 73 (2012); http://dx.doi.org/10.1063/1.4730691
VIEW DESCRIPTIO N
Influence of void fraction on plutonium recycling in BWR
R. Surbakti, A. Waris, K. Basar, S. Permana and R. Kurniadi
Source: AIP Conf. Proc. 1454, 77 (2012); http://dx.doi.org/10.1063/1.4730692
VIEW DESCRIPTIO N
COMPUTATIONAL METHODS IN PHYSICS
Inverse scattering pre-stack depth imaging and it's comparison to some depth migration
methods for imaging rich fault complex structure
Bagus Endar B. Nurhandoko, Indriani Sukmana, Syahrul Mubarok, Agus Deny, Sri Widowati and Rizal Kurniadi
Source: AIP Conf. Proc. 1454, 83 (2012); http://dx.doi.org/10.1063/1.4730693
VIEW DESCRIPTIO N
Design of small gas cooled fast reactor with two region of natural Uranium
fuel fraction
Menik Ariani, Zaki Su’ud, Abdul Waris, Khairurrijal, Fiber Monado et al.
Citation: AIP Conf. Proc. 1454, 69 (2012); doi: 10.1063/1.4730690
View online: http://dx.doi.org/10.1063/1.4730690
View Table of Contents: http://proceedings.aip.org/dbt/dbt.jsp?KEY=APCPCS&Volume=1454&Issue=1
Published by the American Institute of Physics.
Additional information on AIP Conf. Proc.
Journal Homepage: http://proceedings.aip.org/
Journal Information: http://proceedings.aip.org/about/about_the_proceedings
Top downloads: http://proceedings.aip.org/dbt/most_downloaded.jsp?KEY=APCPCS
Information for Authors: http://proceedings.aip.org/authors/information_for_authors
Downloaded 01 Nov 2012 to 167.205.22.105. Redistribution subject to AIP license or copyright; see http://proceedings.aip.org/about/rights_permissions
Design of Small Gas Cooled Fast Reactor with Two Region
of Natural Uranium Fuel Fraction
Menik Ariani*a,b , Zaki Su’uda, Abdul Warisa, Khairurrijala, Fiber Monadoa,b,
Hiroshi Sekimotoc, Sinsuke Nakayamac
a
Department of Physics Bandung Institute of Technology, Jl. Ganesha 10, Bandung 40134, Indonesia,
Physics Department, Sriwijaya University,Kampus Indralaya, Ogan Ilir, Sumatera Selatan, Indonesia
c
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1-N1-17, Ookayama, Meguro-ku
152-8550, Japan
*
E-mail: menikariani@students.itb.ac.id
b
Abstract A design study of small Gas Cooled Fast Reactor with two region fuel has been performed. In this study,
design GCFR with Helium coolant which can be continuously operated by supplying mixed Natural Uranium without
fuel enrichment plant or fuel reprocessing plant. The active reactor cores are divided into two region fuel i.e. 60% fuel
fraction of Natural Uranium as inner core and 65% fuel fraction of Natural Uranium as outer core. Each fuel core
regions are subdivided into ten parts (region-1 until region-10) with the same volume in the axial direction. The fresh
Natural Uranium initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each
region-1 filled by fresh Natural Uranium. This concept is basically applied to all regions in both cores area, i.e. shifted
the core of ith region into i+1 region after the end of 10 years burn-up cycle. For the next cycles, we will add only
Natural Uranium on each region-1. The burn-up calculation is performed using collision probability method PIJ (cell
burn-up calculation) in SRAC code which then given eight energy group macroscopic cross section data to be used in
two dimensional R-Z geometry multi groups diffusion calculation in CITATION code. This reactor can results power
thermal 600 MWth with average power density i.e. 80 watt/cc. After reactor start-up the operation, furthermore reactor
only needs Natural Uranium supply for continue operation along 100 years. This calculation result then compared with
one region fuel design i.e. 60% and 65% fuel fraction. This core design with two region fuel fraction can be an option
for fuel optimization.
Keywords: two region, fuel fraction, Natural Uranium, Modified CANDLE
PACS: 28.20.Gd
sustainability, safety and reliability, economics and
proliferation resistance and physical protection of the
future nuclear fuel cycle.
Conceptual design GCFR with Helium coolant
which can be continuously operated by supplying
Natural Uranium without fuel enrichment plant or fuel
reprocessing plant. The CANDLE (Constant Axial
shape of Neutron flux, nuclide densities and power
shape During Life of Energy producing reactor) burnup strategy can be applied to several reactors, when
the infinite neutron multiplication factor of fuel
element of the reactor changes along burn-up as the
followings [1,2].
In this case CANDLE burn-up strategy is slightly
modified by introducing discrete regions. The reactor
cores are subdivided into several parts with the same
volume in the axial directions. The previous study
shows that Modified CANDLE concept was
INTRODUCTION
The Natural Uranium fuel cycle remains an
attractive option for current and prospective reactors,
for a variety of reasons. The fuel itself is simple,
consisting of only seven basic components, and can be
easily manufactured in many countries. The use of
natural uranium avoids a requirement for Uraniumenrichment capability. It also avoids the creation of
depleted-Uranium enrichment-plant.
In the present paper, a Modified CANDLE burn-up
calculation for small and long life Gas Cooled Fast
Reactor was described. Gas Cooled Fast Reactor
included in the Generation-IV (GEN-IV) reactor
systems are being developed to provide sustainable
energy resources that meet future energy demand in a
reliable, safe, and proliferation-resistant manner.
These innovative reactor systems aim at the
International Conference on Physics and its Applications
AIP Conf. Proc. 1454, 69-72 (2012); doi: 10.1063/1.4730690
© 2012 American Institute of Physics 978-0-7354-1055-8/$30.00
69
Downloaded 01 Nov 2012 to 167.205.22.105. Redistribution subject to AIP license or copyright; see http://proceedings.aip.org/about/rights_permissions
successfully applicable
Natural Uranium as
technology allows for
operating, furthermore
Uranium as fuel cycle.
to long-life fast reactor with
fuel cycle input [4]. This
the reactor which has been
it only need supply Natural
burn-up in SRAC code which then given eight energy
group macroscopic cross section data to be used in two
dimensional R-Z geometry multi groups diffusion
calculation. The average power density in each region
resulted from the diffusion calculation is then brought
back to SRAC code for cell burn-up calculation. This
iteration is repeated until the convergence is reached.
DESIGN CONCEPT
The reactor core is that part of the reactor where
the nuclear fuel assemblies are located and the fission
reaction takes place. Design was optimized by division
of core into two regions with different fuel fraction.
Inner core with 65% fuel fraction and outer core with
65% fuel fraction. Detail specification for the reactor
design given by Table 1.
TABLE 1. Reactor Core Design Parameter
Parameter
Value/Description
Power
600 MWth
Fuel material
Nitride- Nat. Uranium
Cladding material
Stainless Steel
Coolant material
Helium
Inner core volume fraction
60% :10% : 30%
Outer core volume fraction
65% :10% : 25%
Fuel pin diameter
1.4 cm
Active core radial width
120 cm
Active core axial height
350 cm
Radial Reflector width
50 cm
Sub cycle length
10 years
In this design the active reactor core are divided
into two region fuel, inner core was contains Natural
Uranium with 60% fuel fraction and outer core with
65% fuel fraction (Fig. 1). Both cores area were
subdivided into ten parts (region-1 until region-10)
with the same volume in the axial direction. In
Modified CANDLE burn-up scheme strategy (Fig. 2),
the fresh Natural Uranium is initially put in region-1,
after one cycle of 10 years of burn-up it is shifted to
region-2 and the region-1 is filled by fresh natural
Uranium fuels [4]. This concept is basically applied to
all regions in fuel cores area, i.e. shifted the core of i th
region into i+1 region after the end of 10 years burnup cycle. Furthermore for the next cycles, we will add
only Natural Uranium on region-1, so that this reactor
will be able to operate until 100 years with only nitride
Natural Uranium as fuel cycle input.
FIGURE 1. Reactor Core configuration.
CALCULATION METHOD
The calculation is performed using SRAC code
system (SRAC-CITATION system) with JENDL-3.2
nuclear data library [3]. At the beginning we assume
the power density level in each region and then we
perform the burn-up calculation using the assumed
data. The burn-up calculation is performed using cell
FIGURE 2. Modified CANDLE burn-up scheme.
.
70
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Fig. 4 shows infinite multiplication factor change
during burn-up history. It is shown that the infinite
multiplication factor continuously increases. Inner
core value increase more rapidly than others. The
change of the slope is related to the position shift (see
Fig.2).This condition is related to burn-up level change
in Fig. 5.
RESULT
The results of calculation with modified CANDLE
strategy for 100 years burn-up are presented as
follows. Fig. 3 shows effective multiplication in sub
cycle. For the reactor with 60%, 65% and two region
fuel (60/65)%, keff value always above 1.0. It can be
indicates that the reactor can operate 10 years without
refueling.
1.4
1.2
1.0
1.04
k-infinite
effective mult. constant
1.05
1.03
0.8
0.6
60%
1.02
60%
0.4
reg60
65%
1.01
65%
0.2
reg65
(60/65)%
1.00
0.0
0
1
2
3
time (x2 years)
4
5
-
FIGURE 3. Effective multiplication factor in sub-cycle
20
40
60
burn-up period (years)
80
100
FIGURE 4. k-infinite Change during Burn-up.
TABLE 1. Initially fuel material composition in each region
Nat. U-60% (inner core)
% of Pu-239
Region-1
0
Region-2
2.0
Region-3
3.0
Region-4
4.4
Region-5
6.5
Region-6
8.1
Region-7
8.2
Region-8
7.5
6.6
Region-9
Region-10
6.0
Table 2 shows the initially composition material
that is atomic percent of Plutonium-239 in core region
(both inner core and outer core). After reactor start up
the operation with this condition, furthermore reactor
only needs Natural Uranium supply for continue
operation until 100 years burn-up.
Figure 5 shows the burn-up level increases slowly
up to 30 years of burn-up. But after that, along with
significant accumulation of Plutonium, the burn- up
level increases significantly. Change from fuel U-238
that have not able to generate power to become the
main fuel containing enough Pu-239 that producing
great power.
Nat. U-65% (outer core)
Region-1
Region-2
Region-3
Region-4
Region-5
Region-6
Region-7
Region-8
Region-9
Region-10
% of Pu-239
0
1.6
2.2
2.7
3.8
5.6
7.3
8.2
8.3
7.9
5.0E+5
burn-up level (MWD/ton)
4.5E+5
4.0E+5
3.5E+5
3.0E+5
2.5E+5
2.0E+5
1.5E+5
60%
65%
reg60
reg65
1.0E+5
5.0E+4
0.0E+0
0
20
40
60
burn-up period (years)
80
100
FIGURE 5. Burn-up Level change during Burn-up
71
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density value higher than single core without division.
The average power density was 80.0 watt/cc.
Figure 6 shows the axial power distribution for all
core configurations. Average power density for core
with 60% fuel fraction is 75.7 watt/cc and core with
65% fuel fraction is 75.8 watt/cc. The value of average
power density for core with two region fuel (60/65)%
was higher i.e. 80.0 watt/cc.
REFERENCES
1. H. Sekimoto, Y. Yan, Annals of Nuclear Energy 35, 18 –
36 (2007).
2. H. Sekimoto, K. Ryu, Y. Yoshimura, Nuclear Science
and Engineering 139, 306 - 317 (2001).
3. K. Okumura, K. Kaneko and K. Tsuchihashi, SRAC95;
General Purpose Neutronics Code System, JAERIData/Code 96-015, Japan Atomic Energy Research
Institute, Japan, 1996.
4. Z. Su’ud, H. Sekimoto, IJNEST 5, 347 – 358 (2010).
power density (watt/cc)
250
200
150
100
50
FIGURE 6. Axial Power Distribution for All Core
Configuration
Figure 7 shows the power distribution in axial
direction. It indicates that in 10 years operation there
was some shift in the density resources toward more
less of burn-up level.
power density (watt/cc)
250
BOC
200
150
100
EOC
50
0
FIGURE 4. Reactor Core configuration
0
25
50
75
100 125
z (cm)
150
175
200
225
FIGURE 7. Axial Power Distribution in sub-cycle
CONCLUSION
Design of Small and Long-life Gas Cooled Fast
Reactor with Helium coolant has been investigated.
The reactor with thermal power 600 MWth was
designed for 100 years long-life. Using Modified
CANDLE burn-up strategy, a reactor start up the
operation, furthermore this reactor only needs Natural
Uranium supply for continue operation along 100
years without refueling in sub-cycle. optimizations
performed by the division of fuel core i.e inner core
(60% fuel fraction) and outer core (65% fuel fraction).
This core configuration was result average power
72
Downloaded 01 Nov 2012 to 167.205.22.105. Redistribution subject to AIP license or copyright; see http://proceedings.aip.org/about/rights_permissions
INTERNATIONAL CONFERENCE ON PHYSICS AND ITS
APPLICATIONS: (ICPAP 2011)
Conference date: 10–11 November 2011
Location: Bandung, Indonesia
ISBN: 978-0-7354-1055-8
Editors: Khairul Basar and Sparisoma Viridi
Volume number: 1454
Published: 20 June 2012
Front Matter
Source: AIP Conf. Proc. 1454 (2012); http://dx.doi.org/10.1063/v1454.frontmatter
VIEW DESCRIPTIO N
Preface: International Conference on Physics and Its Applications (ICPAP 2011)
Khairul Basar and Sparisoma Viridi
Source: AIP Conf. Proc. 1454, 1 (2012); http://dx.doi.org/10.1063/1.4730673
VIEW DESCRIPTIO N
INVITED PAPERS
Direct observation of local chemical surface properties by scanning tunneling microscopy
Harry E. Hoster
Source: AIP Conf. Proc. 1454, 9 (2012); http://dx.doi.org/10.1063/1.4730676
VIEW DESCRIPTIO N
Accurate force measurement using optical interferometer
Yusaku Fujii
Source: AIP Conf. Proc. 1454, 15 (2012); http://dx.doi.org/10.1063/1.4730677
VIEW DESCRIPTIO N
Appropriate observables for investigating narrow resonances in kaon photoproduction off a
proton
T. Mart
Source: AIP Conf. Proc. 1454, 19 (2012); http://dx.doi.org/10.1063/1.4730678
VIEW DESCRIPTIO N
ASTROPHYSICS AND HIGH ENERGY PHYSICS
The characteristics of solar wind parameters during minimum periods of solar cycle 24 and
impact on geoeffectiveness
Dhani Herdiwijaya
Source: AIP Conf. Proc. 1454, 25 (2012); http://dx.doi.org/10.1063/1.4730679
VIEW DESCRIPTIO N
Morning twilight measured at Bandung and Jombang
Eka Puspita Arumaningtyas, Moedji Raharto and Dhani Herdiwijaya
Source: AIP Conf. Proc. 1454, 29 (2012); http://dx.doi.org/10.1063/1.4730680
VIEW DESCRIPTIO N
The surface distribution of solar energetic particles on the Earth and Southern Atlantic
Anomaly
Febi Trihermanto and Dhani Herdiwijaya
Source: AIP Conf. Proc. 1454, 32 (2012); http://dx.doi.org/10.1063/1.4730681
VIEW DESCRIPTIO N
The possible range arc of vision for Aphelion and Perihelion group of Hilal visibility
Moedji Raharto and Novi Sopwan
Source: AIP Conf. Proc. 1454, 35 (2012); http://dx.doi.org/10.1063/1.4730682
VIEW DESCRIPTIO N
Population density effect on radio frequencies interference (RFI) in radio astronomy
Roslan Umar, Zamri Zainal Abidin, Zainol Abidin Ibrahim, Mohd Saiful Rizal Hassan, Zulfazli Rosli and Zety
Shahrizat Hamidi
Source: AIP Conf. Proc. 1454, 39 (2012); http://dx.doi.org/10.1063/1.4730683
VIEW DESCRIPTIO N
Indication of radio frequency interference (RFI) sources for solar burst monitoring in Malaysia
Z. S. Hamidi, Z. Z. Abidin, Z. A. Ibrahim and N. N. M. Shariff
Source: AIP Conf. Proc. 1454, 43 (2012); http://dx.doi.org/10.1063/1.4730684
VIEW DESCRIPTIO N
Nonminimal derivative coupling in five dimensional universal extra dimensions and recovering
the cosmological constant
Agus Suroso, Freddy P. Zen and Bobby E. Gunara
Source: AIP Conf. Proc. 1454, 47 (2012); http://dx.doi.org/10.1063/1.4730685
VIEW DESCRIPTIO N
NUCLEAR PHYSICS AND APPLICATIONS
The assessment of consistency using penetrometer and apparent diffusion coefficient (ADC)
value using diffusion weighted magnetic resonance imaging (DW-MRI) from polyvinyl alcohol
(PVA) formed by freezing-thawing cycle
Yanurita Dwihapsari, Dita Puspita Sari and Darminto
Source: AIP Conf. Proc. 1454, 53 (2012); http://dx.doi.org/10.1063/1.4730686
VIEW DESCRIPTIO N
Determination of Cu, Zn and Pb in scalp hair from a selected population in Penang using the
XRF method
Khalid Saleh Ali Aldroobi, A. Shukri, Eid Mahmoud Eid Abdel Munem, Sabar Bauk, Mohammad Wasef
Marashdeh and Yahye Abbas Amin
Source: AIP Conf. Proc. 1454, 57 (2012); http://dx.doi.org/10.1063/1.4730687
VIEW DESCRIPTIO N
Impact of curved surface for clinical plan verification in intensity modulated radiation therapy
using 2d array I'mRT MatriXX
Saleh Alashraha, Sivamany Kandaiya and Soon Keong Cheng
Source: AIP Conf. Proc. 1454, 61 (2012); http://dx.doi.org/10.1063/1.4730688
VIEW DESCRIPTIO N
Computational study: Reduction of iron corrosion in lead coolant of fast nuclear reactor
Artoto Arkundato, Zaki Su’ud, Mikrajuddin Abdullah and Widayani
Source: AIP Conf. Proc. 1454, 65 (2012); http://dx.doi.org/10.1063/1.4730689
VIEW DESCRIPTIO N
Design of small gas cooled fast reactor with two region of natural Uranium fuel fraction
Menik Ariani, Zaki Su’ud, Abdul Waris, Khairurrijal, Fiber Monado, Hiroshi Sekimoto and Sinsuke Nakayama
Source: AIP Conf. Proc. 1454, 69 (2012); http://dx.doi.org/10.1063/1.4730690
VIEW DESCRIPTIO N
Preliminary study on direct recycling of spent BWR fuel in BWR system
A. Waris, Sumbono, Dythia Prayudhatama, Novitrian and Zaki Su’ud
Source: AIP Conf. Proc. 1454, 73 (2012); http://dx.doi.org/10.1063/1.4730691
VIEW DESCRIPTIO N
Influence of void fraction on plutonium recycling in BWR
R. Surbakti, A. Waris, K. Basar, S. Permana and R. Kurniadi
Source: AIP Conf. Proc. 1454, 77 (2012); http://dx.doi.org/10.1063/1.4730692
VIEW DESCRIPTIO N
COMPUTATIONAL METHODS IN PHYSICS
Inverse scattering pre-stack depth imaging and it's comparison to some depth migration
methods for imaging rich fault complex structure
Bagus Endar B. Nurhandoko, Indriani Sukmana, Syahrul Mubarok, Agus Deny, Sri Widowati and Rizal Kurniadi
Source: AIP Conf. Proc. 1454, 83 (2012); http://dx.doi.org/10.1063/1.4730693
VIEW DESCRIPTIO N
Design of small gas cooled fast reactor with two region of natural Uranium
fuel fraction
Menik Ariani, Zaki Su’ud, Abdul Waris, Khairurrijal, Fiber Monado et al.
Citation: AIP Conf. Proc. 1454, 69 (2012); doi: 10.1063/1.4730690
View online: http://dx.doi.org/10.1063/1.4730690
View Table of Contents: http://proceedings.aip.org/dbt/dbt.jsp?KEY=APCPCS&Volume=1454&Issue=1
Published by the American Institute of Physics.
Additional information on AIP Conf. Proc.
Journal Homepage: http://proceedings.aip.org/
Journal Information: http://proceedings.aip.org/about/about_the_proceedings
Top downloads: http://proceedings.aip.org/dbt/most_downloaded.jsp?KEY=APCPCS
Information for Authors: http://proceedings.aip.org/authors/information_for_authors
Downloaded 01 Nov 2012 to 167.205.22.105. Redistribution subject to AIP license or copyright; see http://proceedings.aip.org/about/rights_permissions
Design of Small Gas Cooled Fast Reactor with Two Region
of Natural Uranium Fuel Fraction
Menik Ariani*a,b , Zaki Su’uda, Abdul Warisa, Khairurrijala, Fiber Monadoa,b,
Hiroshi Sekimotoc, Sinsuke Nakayamac
a
Department of Physics Bandung Institute of Technology, Jl. Ganesha 10, Bandung 40134, Indonesia,
Physics Department, Sriwijaya University,Kampus Indralaya, Ogan Ilir, Sumatera Selatan, Indonesia
c
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1-N1-17, Ookayama, Meguro-ku
152-8550, Japan
*
E-mail: menikariani@students.itb.ac.id
b
Abstract A design study of small Gas Cooled Fast Reactor with two region fuel has been performed. In this study,
design GCFR with Helium coolant which can be continuously operated by supplying mixed Natural Uranium without
fuel enrichment plant or fuel reprocessing plant. The active reactor cores are divided into two region fuel i.e. 60% fuel
fraction of Natural Uranium as inner core and 65% fuel fraction of Natural Uranium as outer core. Each fuel core
regions are subdivided into ten parts (region-1 until region-10) with the same volume in the axial direction. The fresh
Natural Uranium initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each
region-1 filled by fresh Natural Uranium. This concept is basically applied to all regions in both cores area, i.e. shifted
the core of ith region into i+1 region after the end of 10 years burn-up cycle. For the next cycles, we will add only
Natural Uranium on each region-1. The burn-up calculation is performed using collision probability method PIJ (cell
burn-up calculation) in SRAC code which then given eight energy group macroscopic cross section data to be used in
two dimensional R-Z geometry multi groups diffusion calculation in CITATION code. This reactor can results power
thermal 600 MWth with average power density i.e. 80 watt/cc. After reactor start-up the operation, furthermore reactor
only needs Natural Uranium supply for continue operation along 100 years. This calculation result then compared with
one region fuel design i.e. 60% and 65% fuel fraction. This core design with two region fuel fraction can be an option
for fuel optimization.
Keywords: two region, fuel fraction, Natural Uranium, Modified CANDLE
PACS: 28.20.Gd
sustainability, safety and reliability, economics and
proliferation resistance and physical protection of the
future nuclear fuel cycle.
Conceptual design GCFR with Helium coolant
which can be continuously operated by supplying
Natural Uranium without fuel enrichment plant or fuel
reprocessing plant. The CANDLE (Constant Axial
shape of Neutron flux, nuclide densities and power
shape During Life of Energy producing reactor) burnup strategy can be applied to several reactors, when
the infinite neutron multiplication factor of fuel
element of the reactor changes along burn-up as the
followings [1,2].
In this case CANDLE burn-up strategy is slightly
modified by introducing discrete regions. The reactor
cores are subdivided into several parts with the same
volume in the axial directions. The previous study
shows that Modified CANDLE concept was
INTRODUCTION
The Natural Uranium fuel cycle remains an
attractive option for current and prospective reactors,
for a variety of reasons. The fuel itself is simple,
consisting of only seven basic components, and can be
easily manufactured in many countries. The use of
natural uranium avoids a requirement for Uraniumenrichment capability. It also avoids the creation of
depleted-Uranium enrichment-plant.
In the present paper, a Modified CANDLE burn-up
calculation for small and long life Gas Cooled Fast
Reactor was described. Gas Cooled Fast Reactor
included in the Generation-IV (GEN-IV) reactor
systems are being developed to provide sustainable
energy resources that meet future energy demand in a
reliable, safe, and proliferation-resistant manner.
These innovative reactor systems aim at the
International Conference on Physics and its Applications
AIP Conf. Proc. 1454, 69-72 (2012); doi: 10.1063/1.4730690
© 2012 American Institute of Physics 978-0-7354-1055-8/$30.00
69
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successfully applicable
Natural Uranium as
technology allows for
operating, furthermore
Uranium as fuel cycle.
to long-life fast reactor with
fuel cycle input [4]. This
the reactor which has been
it only need supply Natural
burn-up in SRAC code which then given eight energy
group macroscopic cross section data to be used in two
dimensional R-Z geometry multi groups diffusion
calculation. The average power density in each region
resulted from the diffusion calculation is then brought
back to SRAC code for cell burn-up calculation. This
iteration is repeated until the convergence is reached.
DESIGN CONCEPT
The reactor core is that part of the reactor where
the nuclear fuel assemblies are located and the fission
reaction takes place. Design was optimized by division
of core into two regions with different fuel fraction.
Inner core with 65% fuel fraction and outer core with
65% fuel fraction. Detail specification for the reactor
design given by Table 1.
TABLE 1. Reactor Core Design Parameter
Parameter
Value/Description
Power
600 MWth
Fuel material
Nitride- Nat. Uranium
Cladding material
Stainless Steel
Coolant material
Helium
Inner core volume fraction
60% :10% : 30%
Outer core volume fraction
65% :10% : 25%
Fuel pin diameter
1.4 cm
Active core radial width
120 cm
Active core axial height
350 cm
Radial Reflector width
50 cm
Sub cycle length
10 years
In this design the active reactor core are divided
into two region fuel, inner core was contains Natural
Uranium with 60% fuel fraction and outer core with
65% fuel fraction (Fig. 1). Both cores area were
subdivided into ten parts (region-1 until region-10)
with the same volume in the axial direction. In
Modified CANDLE burn-up scheme strategy (Fig. 2),
the fresh Natural Uranium is initially put in region-1,
after one cycle of 10 years of burn-up it is shifted to
region-2 and the region-1 is filled by fresh natural
Uranium fuels [4]. This concept is basically applied to
all regions in fuel cores area, i.e. shifted the core of i th
region into i+1 region after the end of 10 years burnup cycle. Furthermore for the next cycles, we will add
only Natural Uranium on region-1, so that this reactor
will be able to operate until 100 years with only nitride
Natural Uranium as fuel cycle input.
FIGURE 1. Reactor Core configuration.
CALCULATION METHOD
The calculation is performed using SRAC code
system (SRAC-CITATION system) with JENDL-3.2
nuclear data library [3]. At the beginning we assume
the power density level in each region and then we
perform the burn-up calculation using the assumed
data. The burn-up calculation is performed using cell
FIGURE 2. Modified CANDLE burn-up scheme.
.
70
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Fig. 4 shows infinite multiplication factor change
during burn-up history. It is shown that the infinite
multiplication factor continuously increases. Inner
core value increase more rapidly than others. The
change of the slope is related to the position shift (see
Fig.2).This condition is related to burn-up level change
in Fig. 5.
RESULT
The results of calculation with modified CANDLE
strategy for 100 years burn-up are presented as
follows. Fig. 3 shows effective multiplication in sub
cycle. For the reactor with 60%, 65% and two region
fuel (60/65)%, keff value always above 1.0. It can be
indicates that the reactor can operate 10 years without
refueling.
1.4
1.2
1.0
1.04
k-infinite
effective mult. constant
1.05
1.03
0.8
0.6
60%
1.02
60%
0.4
reg60
65%
1.01
65%
0.2
reg65
(60/65)%
1.00
0.0
0
1
2
3
time (x2 years)
4
5
-
FIGURE 3. Effective multiplication factor in sub-cycle
20
40
60
burn-up period (years)
80
100
FIGURE 4. k-infinite Change during Burn-up.
TABLE 1. Initially fuel material composition in each region
Nat. U-60% (inner core)
% of Pu-239
Region-1
0
Region-2
2.0
Region-3
3.0
Region-4
4.4
Region-5
6.5
Region-6
8.1
Region-7
8.2
Region-8
7.5
6.6
Region-9
Region-10
6.0
Table 2 shows the initially composition material
that is atomic percent of Plutonium-239 in core region
(both inner core and outer core). After reactor start up
the operation with this condition, furthermore reactor
only needs Natural Uranium supply for continue
operation until 100 years burn-up.
Figure 5 shows the burn-up level increases slowly
up to 30 years of burn-up. But after that, along with
significant accumulation of Plutonium, the burn- up
level increases significantly. Change from fuel U-238
that have not able to generate power to become the
main fuel containing enough Pu-239 that producing
great power.
Nat. U-65% (outer core)
Region-1
Region-2
Region-3
Region-4
Region-5
Region-6
Region-7
Region-8
Region-9
Region-10
% of Pu-239
0
1.6
2.2
2.7
3.8
5.6
7.3
8.2
8.3
7.9
5.0E+5
burn-up level (MWD/ton)
4.5E+5
4.0E+5
3.5E+5
3.0E+5
2.5E+5
2.0E+5
1.5E+5
60%
65%
reg60
reg65
1.0E+5
5.0E+4
0.0E+0
0
20
40
60
burn-up period (years)
80
100
FIGURE 5. Burn-up Level change during Burn-up
71
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density value higher than single core without division.
The average power density was 80.0 watt/cc.
Figure 6 shows the axial power distribution for all
core configurations. Average power density for core
with 60% fuel fraction is 75.7 watt/cc and core with
65% fuel fraction is 75.8 watt/cc. The value of average
power density for core with two region fuel (60/65)%
was higher i.e. 80.0 watt/cc.
REFERENCES
1. H. Sekimoto, Y. Yan, Annals of Nuclear Energy 35, 18 –
36 (2007).
2. H. Sekimoto, K. Ryu, Y. Yoshimura, Nuclear Science
and Engineering 139, 306 - 317 (2001).
3. K. Okumura, K. Kaneko and K. Tsuchihashi, SRAC95;
General Purpose Neutronics Code System, JAERIData/Code 96-015, Japan Atomic Energy Research
Institute, Japan, 1996.
4. Z. Su’ud, H. Sekimoto, IJNEST 5, 347 – 358 (2010).
power density (watt/cc)
250
200
150
100
50
FIGURE 6. Axial Power Distribution for All Core
Configuration
Figure 7 shows the power distribution in axial
direction. It indicates that in 10 years operation there
was some shift in the density resources toward more
less of burn-up level.
power density (watt/cc)
250
BOC
200
150
100
EOC
50
0
FIGURE 4. Reactor Core configuration
0
25
50
75
100 125
z (cm)
150
175
200
225
FIGURE 7. Axial Power Distribution in sub-cycle
CONCLUSION
Design of Small and Long-life Gas Cooled Fast
Reactor with Helium coolant has been investigated.
The reactor with thermal power 600 MWth was
designed for 100 years long-life. Using Modified
CANDLE burn-up strategy, a reactor start up the
operation, furthermore this reactor only needs Natural
Uranium supply for continue operation along 100
years without refueling in sub-cycle. optimizations
performed by the division of fuel core i.e inner core
(60% fuel fraction) and outer core (65% fuel fraction).
This core configuration was result average power
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