# Feasibility Studies on Pyro-SFR Closed Fuel Cycle and Direct Disposal of Spent Nuclear Fuel in Line with the Latest National Policy and Strategy of Korea

Authors: Muhammad Minhaj Khan; Jae Min Lee; Jae Hak Cheong; Joo Ho Whang
Journal: Science and Technology of Nuclear Installations
 (2017)

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## Abstract

With a view to providing supportive information for the decision-making on the direction of the future nuclear energy systems in Korea (i.e., direct disposal or recycling of spent nuclear fuel) to be made around 2020, quantitative studies on the spent nuclear fuel (SNF) including transuranic elements (TRUs) and a series of economic analyses were conducted. At first, the total isotopic inventory of TRUs in the SNF to be generated from all thirty-six units of nuclear power plants in operation or under planning is estimated based on the Korean government’s official plan for nuclear power development. Secondly, the optimized deployment strategies are proposed considering the minimum number of sodium cooled-fast reactors (SFRs) needed to transmute all TRUs. Finally, direct disposal and Pyro-SFR closed nuclear energy systems were compared using equilibrium economic model and considering reduction of TRUs and electricity generation as benefits. Probabilistic economic analysis shows that the assumed total generation cost for direct disposal and Pyro-SFR closed nuclear energy systems resides within the range of 13.60~33.94 mills/kWh and 11.40~25.91 mills/kWh, respectively. Dominant cost elements and the range of SFR overnight cost which guarantees the economic feasibility of the Pyro-SFR closed nuclear energy system over the direct disposal option were also identified through sensitivity analysis and break-even cost estimation.


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## Body

## 1. Introduction

As of March 2016, the amount of spent nuclear fuel (SNF) produced from twenty units of pressurized light water reactors (PWRs) and four units of pressurized heavy water reactors (PHWRs) was reported to be about 14,608 metric tons of uranium (MTU) from the whole twenty-four units of Korean nuclear power plants (NPPs) (i.e., PWRs and PHWRs) [1]. The generation of SNF will continually increase since Korea is officially planning to deploy an additional eight units of Advanced Power Reactor 1400 (APR-1400) and four units of Advanced Power Reactor Plus (APR+) type PWRs by 2029 as scheduled in the 7th Basic Plan on Electricity Demand and Supply promulgated in July 2015 [2].Due to the limited capacities of the SNF storage facilities at existing NPPs sites, the Korean government established the Basic Plan on High-level Radioactive Waste Management in July 2016, which specifies the plan for operation of a centralized SNF interim storage facility and a high-level radioactive waste (HLW) disposal facility by 2035 and 2053, respectively [3].In parallel, the Korean government also plans to decide whether or not to commercialize the Pyro-SFR (pyroprocessing-sodium cooled-fast reactor) fuel cycle technology which has been developed since 1997, by around 2020, based upon the result of ongoing feasibility studies as clearly addressed in the Strategy for Technical Development and Demonstration of Future Nuclear Energy System published in July 2016 [4]. Accordingly, the national direction of the back-end fuel cycle is to be decided in the next few years.Feasibilities of direct disposal and Pyro-SFR fuel cycle options based upon the national policy and strategies may provide an important input for the Korean government in deliberating optimized fuel cycle directions. A number of quantitative and economic studies have been reported on the back-end of fuel cycle options for Korea [5–21]. However, most of the previous studies were conducted based upon the assumptions proposed by the investigators rather than upon the official national policy [6–8, 14–16]. In addition, neither detailed estimation of the total amount of SNF and TRUs in terms of radioactivity nor relative radiological toxicities of the SNF to be produced from all units of Korean NPPs have been openly reported. Though a few investigators have calculated the anticipated cost for a nuclear fuel cycle in Korea, no detailed economic feasibility studies have been reported on the overall costs and benefits from open or closed fuel cycle nuclear energy systems being considered in Korea [11–17]. In this context, the electricity generation from SFRs as well as NPPs (i.e., PWRs and PHWRs) could be considered as a potential benefit from the fuel cycle.Thus, the main objective of this study is set to support the decision-making on the future nuclear fuel cycle options in Korea to be made by around 2020 through providing the following information:(i)
Total amount of SNF and TRUs (237Np, 241Am, Am242m, Am243, Cm242, and Cm244 and other plutonium isotopes such as Pu238, Pu239, Pu240, Pu241, and Pu242) to be accumulated in accordance with the latest national policy.(ii)
Time-dependent variations of radiotoxicity due to TRUs in SNF in the long term.(iii)
Optimal deployment strategies of SFRs to transmute the total inventory of TRUs efficiently.(iv)
Economic feasibilities on the overall costs and benefits of open or closed fuel cycle options using probabilistic economic analysis.


## 2. Materials and Methodology

### 2.1. Calculation of Maximum Inventory of SNF and Radioactivity of TRUs

In this study, the Nuclear Fuel Cycle Simulation System (NFCSS) developed by the International Atomic Energy Agency (IAEA) was used to estimate the amount of SNF and TRUs from Korean NPPs. The NFCSS is a scenario-based computer model widely used for quantitative studies on various nuclear fuel cycle scenarios [22–24].A fuel depletion model known as Calculation Actinide Inventory (CAIN) to perform isotopic depletion and decay calculations to solve Bateman’s equations for a point assembly using one group neutron cross section as shown in (1) was adopted in the NFCSS.(1)dNidt=-∑jλii→j+σii→jφ-Ni+∑j≠iλjj→i+σjj→iφNj,where Ni and Nj are the atomic contents of isotopes i and j, respectively; λii→j and λjj→i are the decay constants of nuclides i and j which decay to i (1/s), respectively; σii→j and σjj→i are the transmutation cross sections from isotope i to j (barn) and from isotope j to i (barn), respectively; and φ is the average neutron flux (n/(s·cm2)).Figure1 shows the transmutation chains implemented in CAIN of the NFCSS to calculate the isotopic composition of SNF [25, 26].Figure 1
Simplified transmutation model adopted in CAIN [25].First, calculation was done by using the NFCSS to estimate the generation of SNF including isotopes of plutonium (Pu) and MAs (minor actinides) from twenty-four units of NPPs in operation as of March 2016. As eight units of APR-1400 and four units of APR+ type PWRs will be added by the end of 2029, future estimation for the generation of the SNF from thirty-six units of NPPs by considering their initial design lifetimes (i.e., 30, 40, 60, and 60 years for PHWR, PWR, APR-1400, and APR+, resp.) was made. As the thirty-sixth NPP (APR+) will reach its initial design lifetime of sixty years by the end of 2089, estimation of the inventory of SNF and TRUs has been made by the year of 2089 as a reference year [2].In order to predict the maximum inventory of SNF and TRUs to be produced from all Korean NPPs, twenty years of continued operations of NPPs after termination of their initial design lifetimes were additionally assumed [8]. However, Kori Unit 1 whose initial design lifetime has been already extended for ten years (i.e., from 2007-06-19 to 2017-06-18) was shut down permanently on June 19, 2017, in accordance with the government policy [2]. In addition, the second term of continued operation of 10 years for Wolsong Unit 1 is assumed, of which its first continued operation until 2022-11-20 was approved in 2015. As the thirty-sixth NPP (APR+) will reach its extended design lifetime by the end of 2109, the potential maximum inventory of SNF and TRUs was estimated by the year of 2109 as another reference year.Table1 shows the full list of all units of Korean NPPs (PWRs, PHWRs) which have been already deployed or will be deployed by 2029, along with the time of commercial operation and termination of initial and extended design lifetime [27].Table 1
Dates of commercial operation and initial and to-be-extended design lifetimes for thirty-six units of Korean NPPs [27].
Number
Reactor
Electric power (MWe∗)
Date of
Commercial operation
End of initial design lifetime
End of extended design lifetime assumed
1
Kori-1
587
1978-04-29
2017-06-19∗
No further extension∗∗
2
Kori-2
650
1983-07-25
2023-07-25
2043-07-25
3
Kori-3
950
1985-09-30
2025-09-30
2045-09-30
4
Kori-4
950
1986-04-29
2026-04-29
2046-04-29
5
Shin Kori-1
1000
2011-02-28
2051-02-28
2071-02-28
6
Shin Kori-2
1000
2012-07-20
2052-07-20
2072-07-20
7
Shin Wolsong-1
1000
2012-07-31
2052-07-31
2072-07-31
8
Shin Wolsong-2
1000
2015-07-24
2055-07-24
2075-07-24
9
Hanul-1
950
1988-09-10
2028-09-10
2048-09-10
10
Hanul-2
950
1989-09-30
2029-09-30
2049-09-30
11
Hanul-3
1000
1998-08-11
2038-08-11
2058-08-11
12
Hanul-4
1000
1999-12-03
2039-12-03
2059-12-03
13
Hanul-5
1000
2004-12-31
2044-12-31
2064-12-31
14
Hanul-6
1000
2005-04-22
2045-04-22
2065-04-22
15
Hanbit-1
950
1986-08-25
2026-08-25
2046-08-25
16
Hanbit-2
950
1987-06-10
2027-06-10
2047-06-10
17
Hanbit-3
1000
1995-03-31
2035-03-31
2055-03-31
18
Hanbit-4
1000
1996-01-01
2036-01-01
2056-01-01
19
Hanbit-5
1000
2002-05-21
2042-05-21
2062-05-21
20
Hanbit-6
1000
2002-12-24
2042-12-24
2062-12-24
21
Wolsong-1
679
1983-04-22
2022-01-01∗∗∗
2033-04-22∗∗
22
Wolsong-2
700
1997-07-01
2027-07-01
2047-07-01
23
Wolsong-3
700
1998-07-01
2028-07-01
2048-07-01
24
Wolsong-4
700
1999-10-01
2029-10-01
2049-10-01
25
Shin Kori-3
1400
2016-04-01
2076-04-01
2096-04-01
26
Shin Kori-4
1400
2017-02-01
2077-02-01
2097-02-01
27
Shin Kori-5
1400
2021-03-01
2081-03-01
2101-03-01
28
Shin Kori-6
1400
2022-03-01
2082-03-01
2102-03-01
29
Shin Hanul-1
1400
2017-04-01
2077-04-01
2097-04-01
30
Shin Hanul-2
1400
2018-02-01
2078-02-01
2098-02-01
31
Shin Hanul-3
1400
2022-12-01
2082-12-01
2102-12-01
32
Shin Hanul-4
1400
2023-12-01
2083-12-01
2103-12-01
33
Cheonji-1
1500
2026-12-01
2086-12-01
2106-12-01
34
Cheonji-2
1500
2027-12-01
2087-12-01
2107-12-01
35
Shin Kori-7
1500
2028-12-01
2088-12-01
2108-12-01
36
Shin Kori-8
1500
2029-12-01
2089-12-01
2109-12-01
M
W
e
∗: megawatt electric. Kori∗∗ Unit 1 is assumed to be shut down on June 19, 2017, permanently. Second∗∗∗ continued operation of 10 years is assumed for Wolsong Unit 1.The time-dependent material flow of SNF for each NPP throughout its lifetime is calculated by MS Excel™ spreadsheet based upon the basic information on the Korean NPPs as shown in Table1 and the calculation results of the NFCSS such as the amount of SNF including isotopic composition of TRUs to be generated from each Korean NPP per cycle.


### 2.2. Calculation of Nominal Radiotoxicities

In order to quantify the radiological hazard from each nuclide of TRUs and/or overall hazard from multiple nuclides, a few nominal expressions of radiotoxicity or radiotoxicity index for SNF were reported [28]. In this study, the time-variant nominal radiotoxicity index (in Sv or Sv/g) of SNF was proposed as(2)Radiotoxicity  Index=∑iAi·e-λit·EDCing,ior∑iCi·e-λit·EDCing,i(3)Ai=λi·Ni=ln⁡2T1/2,i·mi·NAMi,where Ai is the radioactivity of a TRU nuclide i (Bq), Ci is the radioactivity concentration of nuclide i (Bq/g), EDCing,i is the effective dose coefficient to an adult age group for ingestion (Sv/Bq), λi is the decay constant of nuclide i (1/y), t is the elapsed time from discharge of the SNF from reactor core (y), Ni is the number of nuclides i, mi is the mass of nuclide i (g), NA is Avogadro’s number (6.02×1023 /mol), Mi is the atomic mass of TRU nuclide i (g/mol), and T1/2,i is the half-life of TRU nuclide i (y).Only ingestion rather than inhalation pathway is considered in (2), since SNF is to be disposed of in deep geological media under direct disposal scenario and the volatilities of the actinides are low enough [29]. The values for Ai and Ci in (2) can be obtained from the nuclide-specific total inventory of TRUs in Bq and total mass of SNF calculated by use of the NFCSS in terms of grams. The values of EDCing,i can be found in a volume of the official publications of the International Commission on Radiological Protection (ICRP) [30].The radiotoxicity of SNF is known to be controlled by fission products for the first 300 years after being discharged from the reactor core, but long-lived actinides contribute most to the radiotoxicity after 300 years [29]. Therefore, this study mainly focuses on the ingestion radiotoxicity indices for long-lived actinides rather than those for fission products.


### 2.3. Establishment of Strategic Scenarios for Transmutation of TRUs by SFRs

In order to compare the Pyro-SFR fuel cycles with direct disposal options and further to find optimized options for deployment of SFRs to transmute TRUs produced from all units of PWRs and PHWRs, a set of comparative scenarios are proposed as shown in Table2.Table 2
Assumed strategic scenarios for transmutation of TRUs in SNF.
Case
Scenario
Direct disposal/recycle
Design lifetime
SFR’s CR
NPPs (PWRs and PHWRs)
SFR
I
SC-1
Direct disposal
Design lifetime
N/A
N/A
SC-2
Direct disposal
+20 y
N/A
N/A
II
SC-3
Recycle
Design lifetime
Design lifetime
0.46
SC-4
Recycle
Design lifetime
Design lifetime
0.6
III
SC-5
Recycle
+20 y
Design lifetime
0.46
SC-6
Recycle
+20 y
Design lifetime
0.6
IV
SC-7
Recycle
+20 y
+20 y
0.46
SC-8
Recycle
+20 y
+20 y
0.6
SC: scenario; CR: conversion ratio; N/A: not applicable.While scenarios 1 and 2 are for the direct disposal of SNF, the remaining six scenarios are proposed to compare the effectiveness of the possible options for recycling of SNF in connection with SFRs. It was also assumed that the metallic SNF discharged from SFRs will be recycled in the Pyro-SFR fuel cycle based upon past reference studies [12, 13, 31].Korea Atomic Energy Research Institute (KAERI) has been developing pyroprocessing technology in connection with SFR with a view to reducing the volume and the radiotoxicity of HLW (i.e., SNF) and thus to reducing the land area needed for direct disposal of SNF in deep geological formations [4].It is also noted that the time needed for cooling the SNF (i.e., at least five years for the SNF from PWR and PHWR) prior to pyroprocessing has been fully covered in this study, since enough amount of sufficiently cooled-down SNF produced from twenty-five units of NPPs since 1978 is already available for pyroprocessing in Korea [31]. Furthermore, the Korean government plans to commercialize a pyroprocessing facility along with SFR fuel fabrication plant by 2025 and then to deploy the first unit of SFR after three years later by 2028, while just about 8 months is reported to be needed for SFR fuel fabrication [6, 32]. Accordingly, it can be said that the SFR fuel fabrication time has been already taken into consideration in this study.The values of characteristic parameters of representative SFRs listed in Table3 for transmutation of TRUs in effective ways were obtained from a few design studies on SFRs, which were used for calculations in this study [33, 34]. The characteristic data for SFR-1 and SFR-2 are generally taken from [33] and [34], respectively; however, the thermal efficiency of SFR-2 is assumed to be the same as SFR-1 since the specific thermal efficiency of SFR-2 is not available in the literature review.Table 3
Characteristics of the reference SFRs.
Reactor design
SFR-1
SFR-2
Unit
Electric power
600
MWe
Thermal efficiency
39.38
%
Thermal power
1523.4
MWth
Capacity factor
85
%
Cycle length
332
EFPD
Design lifetime (normal)
60
Years
Design lifetime (extended)
80
Years
Conversion ratio
0.46
0.6
—
Number of batches
6
4
—
Discharge burnup
217
116.3
GWD/MTHM
TRU consumption rate
530
307.1
kg/cycle
Fuel type
TRU-W-10Zr metal
TRU-U-10Zr metal
Wt.%
Annual electricity generation
4778.62
4770.41
GWh
MWth: megawatt thermal; EFPD: effective full-power day; GWD: gigawatt days; MTHM: metric ton heavy metal; Kg: kilogram; Wt.%: weight percent; GWh: gigawatt hour.For the effective transmutation of TRUs, SFRs with CR = 0.46 and 0.6 have been assumed to be coupled with pyroprocessing in order to transmute all transuranic inventory generation from NPPs. The impact of CR on the SFR was determined by the consumption of TRUs as it is reported that the SFR with higher CR burns less TRUs, while the SFR with lower CR transmutes more. Thus, the minimum number of SFRs to be deployed for transmutation of all the inventory of TRUs can be eventually decided by the value of CR of a specific SFR design [13, 33–35].


### 2.4. Fuel Cycles Cost Estimation

For the sake of nuclear fuel cycle cost estimation, both equilibrium and dynamic models are applicable to assess the economic feasibilities of the different fuel cycle options. The main difference between the two models is that the latter can be used for long-term cost calculation as time elapses while the former is based on the cost calculation at a certain base year [12, 14]. The equilibrium model is capable of providing cost information for prompt decision-making by evaluating the worthiness of a nuclear fuel cycle option quantitatively [12, 14]. Therefore, the equilibrium model was chosen in this study to generate a series of cost information that may be helpful to understand the economic priorities of diverse nuclear fuel cycle options comprehensively and analytically.To evaluate the economic feasibility of a nuclear fuel cycle through equilibrium model, Equations (i) to (xiv) shown in Table12 were proposed to calculate the fuel cycle costs with an assumption of zero discount rate [12]. All the unit cost data are discounted to the base year of 2016 with an inflation rate of 2.08%. In order to calculate the fuel cycle cost (FCC) for each fuel cycle, the individual process cost (i.e., the unit cost multiplied by the material quantity at each step of a fuel cycle) should be calculated. In case of PWR, Equations (i) to (iii) and (vi) can be used to calculate the individual process cost. The total process cost of nuclear fuel cycle can be defined as a summation of all the individual process costs involved in the respective fuel cycle and calculated as such. In case of PWR, PHWR, and Pyro-SFR fuel cycles, the total process cost of nuclear fuel cycle can be calculated by use of Equations (viii) to (x), respectively. The FCC can be defined as the total process cost for a fuel cycle normalized to the electricity generation per unit mass and calculated by dividing the total process cost for each fuel cycle with electricity generation per unit mass. Equations (xi) to (xiv) are used to calculate the FCCs of PWR, PHWR, and Pyro-SFR fuel cycles, respectively. Calculation method and equations are referred from past studies on the equilibrium mass flow and cost model in nuclear fuel cycle [12, 36, 37].In this study, however, Equations (xi) and (xii) were modified in terms of general design parameters of PWRs and PHWRs, while Equations (xiii) and (xiv) were modified based on the specific design parameters of Korean SFRs [33, 34]. Equations (ii) to (vi) were modified by including the cost for disposal of process waste being generated from processes of each fuel cycle [37]. Annual fuel requirement (AFR) in MTHM and annual electricity generation (AEG) in GWh from NPPs (i.e., PWRs and PHWRs) and SFRs are estimated by (4)AFR=P×FCLε×BUAEG=AFR×BU1,000×ε×24h1d,where P is the electric power of a reactor (MWe), FCL is the length of a cycle (EFPD), ε is the thermal efficiency, and BU is the discharge burnup (MWD/MTHM). It is noted that the annual electricity generation for SFR-1 and SFR-2 in Table 3 can be also calculated by using (4).The whole process of economic analysis established and conducted in this study is schematically summarized as shown in Figure2.Figure 2
Overall procedure to estimate cost for economic analysis adopted in this study.


## 2.1. Calculation of Maximum Inventory of SNF and Radioactivity of TRUs

In this study, the Nuclear Fuel Cycle Simulation System (NFCSS) developed by the International Atomic Energy Agency (IAEA) was used to estimate the amount of SNF and TRUs from Korean NPPs. The NFCSS is a scenario-based computer model widely used for quantitative studies on various nuclear fuel cycle scenarios [22–24].A fuel depletion model known as Calculation Actinide Inventory (CAIN) to perform isotopic depletion and decay calculations to solve Bateman’s equations for a point assembly using one group neutron cross section as shown in (1) was adopted in the NFCSS.(1)dNidt=-∑jλii→j+σii→jφ-Ni+∑j≠iλjj→i+σjj→iφNj,where Ni and Nj are the atomic contents of isotopes i and j, respectively; λii→j and λjj→i are the decay constants of nuclides i and j which decay to i (1/s), respectively; σii→j and σjj→i are the transmutation cross sections from isotope i to j (barn) and from isotope j to i (barn), respectively; and φ is the average neutron flux (n/(s·cm2)).Figure1 shows the transmutation chains implemented in CAIN of the NFCSS to calculate the isotopic composition of SNF [25, 26].Figure 1
Simplified transmutation model adopted in CAIN [25].First, calculation was done by using the NFCSS to estimate the generation of SNF including isotopes of plutonium (Pu) and MAs (minor actinides) from twenty-four units of NPPs in operation as of March 2016. As eight units of APR-1400 and four units of APR+ type PWRs will be added by the end of 2029, future estimation for the generation of the SNF from thirty-six units of NPPs by considering their initial design lifetimes (i.e., 30, 40, 60, and 60 years for PHWR, PWR, APR-1400, and APR+, resp.) was made. As the thirty-sixth NPP (APR+) will reach its initial design lifetime of sixty years by the end of 2089, estimation of the inventory of SNF and TRUs has been made by the year of 2089 as a reference year [2].In order to predict the maximum inventory of SNF and TRUs to be produced from all Korean NPPs, twenty years of continued operations of NPPs after termination of their initial design lifetimes were additionally assumed [8]. However, Kori Unit 1 whose initial design lifetime has been already extended for ten years (i.e., from 2007-06-19 to 2017-06-18) was shut down permanently on June 19, 2017, in accordance with the government policy [2]. In addition, the second term of continued operation of 10 years for Wolsong Unit 1 is assumed, of which its first continued operation until 2022-11-20 was approved in 2015. As the thirty-sixth NPP (APR+) will reach its extended design lifetime by the end of 2109, the potential maximum inventory of SNF and TRUs was estimated by the year of 2109 as another reference year.Table1 shows the full list of all units of Korean NPPs (PWRs, PHWRs) which have been already deployed or will be deployed by 2029, along with the time of commercial operation and termination of initial and extended design lifetime [27].Table 1
Dates of commercial operation and initial and to-be-extended design lifetimes for thirty-six units of Korean NPPs [27].
Number
Reactor
Electric power (MWe∗)
Date of
Commercial operation
End of initial design lifetime
End of extended design lifetime assumed
1
Kori-1
587
1978-04-29
2017-06-19∗
No further extension∗∗
2
Kori-2
650
1983-07-25
2023-07-25
2043-07-25
3
Kori-3
950
1985-09-30
2025-09-30
2045-09-30
4
Kori-4
950
1986-04-29
2026-04-29
2046-04-29
5
Shin Kori-1
1000
2011-02-28
2051-02-28
2071-02-28
6
Shin Kori-2
1000
2012-07-20
2052-07-20
2072-07-20
7
Shin Wolsong-1
1000
2012-07-31
2052-07-31
2072-07-31
8
Shin Wolsong-2
1000
2015-07-24
2055-07-24
2075-07-24
9
Hanul-1
950
1988-09-10
2028-09-10
2048-09-10
10
Hanul-2
950
1989-09-30
2029-09-30
2049-09-30
11
Hanul-3
1000
1998-08-11
2038-08-11
2058-08-11
12
Hanul-4
1000
1999-12-03
2039-12-03
2059-12-03
13
Hanul-5
1000
2004-12-31
2044-12-31
2064-12-31
14
Hanul-6
1000
2005-04-22
2045-04-22
2065-04-22
15
Hanbit-1
950
1986-08-25
2026-08-25
2046-08-25
16
Hanbit-2
950
1987-06-10
2027-06-10
2047-06-10
17
Hanbit-3
1000
1995-03-31
2035-03-31
2055-03-31
18
Hanbit-4
1000
1996-01-01
2036-01-01
2056-01-01
19
Hanbit-5
1000
2002-05-21
2042-05-21
2062-05-21
20
Hanbit-6
1000
2002-12-24
2042-12-24
2062-12-24
21
Wolsong-1
679
1983-04-22
2022-01-01∗∗∗
2033-04-22∗∗
22
Wolsong-2
700
1997-07-01
2027-07-01
2047-07-01
23
Wolsong-3
700
1998-07-01
2028-07-01
2048-07-01
24
Wolsong-4
700
1999-10-01
2029-10-01
2049-10-01
25
Shin Kori-3
1400
2016-04-01
2076-04-01
2096-04-01
26
Shin Kori-4
1400
2017-02-01
2077-02-01
2097-02-01
27
Shin Kori-5
1400
2021-03-01
2081-03-01
2101-03-01
28
Shin Kori-6
1400
2022-03-01
2082-03-01
2102-03-01
29
Shin Hanul-1
1400
2017-04-01
2077-04-01
2097-04-01
30
Shin Hanul-2
1400
2018-02-01
2078-02-01
2098-02-01
31
Shin Hanul-3
1400
2022-12-01
2082-12-01
2102-12-01
32
Shin Hanul-4
1400
2023-12-01
2083-12-01
2103-12-01
33
Cheonji-1
1500
2026-12-01
2086-12-01
2106-12-01
34
Cheonji-2
1500
2027-12-01
2087-12-01
2107-12-01
35
Shin Kori-7
1500
2028-12-01
2088-12-01
2108-12-01
36
Shin Kori-8
1500
2029-12-01
2089-12-01
2109-12-01
M
W
e
∗: megawatt electric. Kori∗∗ Unit 1 is assumed to be shut down on June 19, 2017, permanently. Second∗∗∗ continued operation of 10 years is assumed for Wolsong Unit 1.The time-dependent material flow of SNF for each NPP throughout its lifetime is calculated by MS Excel™ spreadsheet based upon the basic information on the Korean NPPs as shown in Table1 and the calculation results of the NFCSS such as the amount of SNF including isotopic composition of TRUs to be generated from each Korean NPP per cycle.


## 2.2. Calculation of Nominal Radiotoxicities

In order to quantify the radiological hazard from each nuclide of TRUs and/or overall hazard from multiple nuclides, a few nominal expressions of radiotoxicity or radiotoxicity index for SNF were reported [28]. In this study, the time-variant nominal radiotoxicity index (in Sv or Sv/g) of SNF was proposed as(2)Radiotoxicity  Index=∑iAi·e-λit·EDCing,ior∑iCi·e-λit·EDCing,i(3)Ai=λi·Ni=ln⁡2T1/2,i·mi·NAMi,where Ai is the radioactivity of a TRU nuclide i (Bq), Ci is the radioactivity concentration of nuclide i (Bq/g), EDCing,i is the effective dose coefficient to an adult age group for ingestion (Sv/Bq), λi is the decay constant of nuclide i (1/y), t is the elapsed time from discharge of the SNF from reactor core (y), Ni is the number of nuclides i, mi is the mass of nuclide i (g), NA is Avogadro’s number (6.02×1023 /mol), Mi is the atomic mass of TRU nuclide i (g/mol), and T1/2,i is the half-life of TRU nuclide i (y).Only ingestion rather than inhalation pathway is considered in (2), since SNF is to be disposed of in deep geological media under direct disposal scenario and the volatilities of the actinides are low enough [29]. The values for Ai and Ci in (2) can be obtained from the nuclide-specific total inventory of TRUs in Bq and total mass of SNF calculated by use of the NFCSS in terms of grams. The values of EDCing,i can be found in a volume of the official publications of the International Commission on Radiological Protection (ICRP) [30].The radiotoxicity of SNF is known to be controlled by fission products for the first 300 years after being discharged from the reactor core, but long-lived actinides contribute most to the radiotoxicity after 300 years [29]. Therefore, this study mainly focuses on the ingestion radiotoxicity indices for long-lived actinides rather than those for fission products.


## 2.3. Establishment of Strategic Scenarios for Transmutation of TRUs by SFRs

In order to compare the Pyro-SFR fuel cycles with direct disposal options and further to find optimized options for deployment of SFRs to transmute TRUs produced from all units of PWRs and PHWRs, a set of comparative scenarios are proposed as shown in Table2.Table 2
Assumed strategic scenarios for transmutation of TRUs in SNF.
Case
Scenario
Direct disposal/recycle
Design lifetime
SFR’s CR
NPPs (PWRs and PHWRs)
SFR
I
SC-1
Direct disposal
Design lifetime
N/A
N/A
SC-2
Direct disposal
+20 y
N/A
N/A
II
SC-3
Recycle
Design lifetime
Design lifetime
0.46
SC-4
Recycle
Design lifetime
Design lifetime
0.6
III
SC-5
Recycle
+20 y
Design lifetime
0.46
SC-6
Recycle
+20 y
Design lifetime
0.6
IV
SC-7
Recycle
+20 y
+20 y
0.46
SC-8
Recycle
+20 y
+20 y
0.6
SC: scenario; CR: conversion ratio; N/A: not applicable.While scenarios 1 and 2 are for the direct disposal of SNF, the remaining six scenarios are proposed to compare the effectiveness of the possible options for recycling of SNF in connection with SFRs. It was also assumed that the metallic SNF discharged from SFRs will be recycled in the Pyro-SFR fuel cycle based upon past reference studies [12, 13, 31].Korea Atomic Energy Research Institute (KAERI) has been developing pyroprocessing technology in connection with SFR with a view to reducing the volume and the radiotoxicity of HLW (i.e., SNF) and thus to reducing the land area needed for direct disposal of SNF in deep geological formations [4].It is also noted that the time needed for cooling the SNF (i.e., at least five years for the SNF from PWR and PHWR) prior to pyroprocessing has been fully covered in this study, since enough amount of sufficiently cooled-down SNF produced from twenty-five units of NPPs since 1978 is already available for pyroprocessing in Korea [31]. Furthermore, the Korean government plans to commercialize a pyroprocessing facility along with SFR fuel fabrication plant by 2025 and then to deploy the first unit of SFR after three years later by 2028, while just about 8 months is reported to be needed for SFR fuel fabrication [6, 32]. Accordingly, it can be said that the SFR fuel fabrication time has been already taken into consideration in this study.The values of characteristic parameters of representative SFRs listed in Table3 for transmutation of TRUs in effective ways were obtained from a few design studies on SFRs, which were used for calculations in this study [33, 34]. The characteristic data for SFR-1 and SFR-2 are generally taken from [33] and [34], respectively; however, the thermal efficiency of SFR-2 is assumed to be the same as SFR-1 since the specific thermal efficiency of SFR-2 is not available in the literature review.Table 3
Characteristics of the reference SFRs.
Reactor design
SFR-1
SFR-2
Unit
Electric power
600
MWe
Thermal efficiency
39.38
%
Thermal power
1523.4
MWth
Capacity factor
85
%
Cycle length
332
EFPD
Design lifetime (normal)
60
Years
Design lifetime (extended)
80
Years
Conversion ratio
0.46
0.6
—
Number of batches
6
4
—
Discharge burnup
217
116.3
GWD/MTHM
TRU consumption rate
530
307.1
kg/cycle
Fuel type
TRU-W-10Zr metal
TRU-U-10Zr metal
Wt.%
Annual electricity generation
4778.62
4770.41
GWh
MWth: megawatt thermal; EFPD: effective full-power day; GWD: gigawatt days; MTHM: metric ton heavy metal; Kg: kilogram; Wt.%: weight percent; GWh: gigawatt hour.For the effective transmutation of TRUs, SFRs with CR = 0.46 and 0.6 have been assumed to be coupled with pyroprocessing in order to transmute all transuranic inventory generation from NPPs. The impact of CR on the SFR was determined by the consumption of TRUs as it is reported that the SFR with higher CR burns less TRUs, while the SFR with lower CR transmutes more. Thus, the minimum number of SFRs to be deployed for transmutation of all the inventory of TRUs can be eventually decided by the value of CR of a specific SFR design [13, 33–35].


## 2.4. Fuel Cycles Cost Estimation

For the sake of nuclear fuel cycle cost estimation, both equilibrium and dynamic models are applicable to assess the economic feasibilities of the different fuel cycle options. The main difference between the two models is that the latter can be used for long-term cost calculation as time elapses while the former is based on the cost calculation at a certain base year [12, 14]. The equilibrium model is capable of providing cost information for prompt decision-making by evaluating the worthiness of a nuclear fuel cycle option quantitatively [12, 14]. Therefore, the equilibrium model was chosen in this study to generate a series of cost information that may be helpful to understand the economic priorities of diverse nuclear fuel cycle options comprehensively and analytically.To evaluate the economic feasibility of a nuclear fuel cycle through equilibrium model, Equations (i) to (xiv) shown in Table12 were proposed to calculate the fuel cycle costs with an assumption of zero discount rate [12]. All the unit cost data are discounted to the base year of 2016 with an inflation rate of 2.08%. In order to calculate the fuel cycle cost (FCC) for each fuel cycle, the individual process cost (i.e., the unit cost multiplied by the material quantity at each step of a fuel cycle) should be calculated. In case of PWR, Equations (i) to (iii) and (vi) can be used to calculate the individual process cost. The total process cost of nuclear fuel cycle can be defined as a summation of all the individual process costs involved in the respective fuel cycle and calculated as such. In case of PWR, PHWR, and Pyro-SFR fuel cycles, the total process cost of nuclear fuel cycle can be calculated by use of Equations (viii) to (x), respectively. The FCC can be defined as the total process cost for a fuel cycle normalized to the electricity generation per unit mass and calculated by dividing the total process cost for each fuel cycle with electricity generation per unit mass. Equations (xi) to (xiv) are used to calculate the FCCs of PWR, PHWR, and Pyro-SFR fuel cycles, respectively. Calculation method and equations are referred from past studies on the equilibrium mass flow and cost model in nuclear fuel cycle [12, 36, 37].In this study, however, Equations (xi) and (xii) were modified in terms of general design parameters of PWRs and PHWRs, while Equations (xiii) and (xiv) were modified based on the specific design parameters of Korean SFRs [33, 34]. Equations (ii) to (vi) were modified by including the cost for disposal of process waste being generated from processes of each fuel cycle [37]. Annual fuel requirement (AFR) in MTHM and annual electricity generation (AEG) in GWh from NPPs (i.e., PWRs and PHWRs) and SFRs are estimated by (4)AFR=P×FCLε×BUAEG=AFR×BU1,000×ε×24h1d,where P is the electric power of a reactor (MWe), FCL is the length of a cycle (EFPD), ε is the thermal efficiency, and BU is the discharge burnup (MWD/MTHM). It is noted that the annual electricity generation for SFR-1 and SFR-2 in Table 3 can be also calculated by using (4).The whole process of economic analysis established and conducted in this study is schematically summarized as shown in Figure2.Figure 2
Overall procedure to estimate cost for economic analysis adopted in this study.


## 3. Results and Discussion

### 3.1. Estimation of Total Inventory of SNF and TRUs

As shown in Table4, the total amount of SNF generated from twenty-four units of operating NPPs as of March 2016 was calculated to be 14,511 metric tons of heavy metal (MTHM) by the NFCSS and the information given in Table 1. The result is quite comparable to the officially reported total inventory of SNF in terms of mass (i.e., 14,608 MTU) accumulated as of March 2016 within the relative error of less than 0.7 percent [1].Table 4
Total amount of SNF to be generated from operation of all units of PWRs and PHWRs planned to be deployed by 2029 per reactor site.
Site
Amount of SNF (MTHM)
As of March 2016
With operation for initial design lifetime (2089)∗
With continued operation for an additional 20 years (2109)∗
This study
[1] (MTU)
Kori (PWRs)
2,201
2,294
11,905
16,282
Hanul (PWRs)
2,049
2,043
9,716
13,697
Hanbit (PWRs)
2,391
2,403
4,502
6,753
Shin-Wolsong (PWRs)
65
54
1,203
1,804
Wolsong (PHWRs)
7,805
7,815
11,514
18,858
Cheonji (PWRs)
—
—
2,878
3,837
Total
14,511
14,608
41,718
61,232
R
e
s
u
l
t
s
∗ for the year of 2089 represent the scenario where continued operation of 36 units of NPPs is not assumed, and those for the year of 2109 are for the scenario where continued operation of all NPPs except for Kori Unit 1 is taken into account. In addition, the contribution of fission products in the spent nuclear fuel is not included in this table.In addition, the overall inventory of SNF to be produced from thirty-six units of NPPs during their initial design lifetimes only and additional continued operation periods (except for Kori Unit 1) were estimated to be 41,718 and 61,232 MTHM, respectively. That is, about 2.9 to 4.2 times more SNF in mass than the present inventory as of March 2016 will be accumulated if an additional eight units of APR-1400 and four units of APR+ type PWRs are deployed by 2029 as officially planned. It is also noted that the potential of continued operation of NPPs up to an additional twenty years may affect the total national inventory of SNF by a factor of 1.47 (≈61,232/41,718).Table5 shows the estimated mass (in grams) of each TRU nuclide which already exists in the total inventory of SNF generated from NPPs as of 2016 and the SNF to be further generated from all NPPs in operation and under construction or planning. It is noted that the mass of fission products is not included in Table 5, since this study mainly focuses on the radiotoxicity of the SNF in the long term as addressed in Section 2.2.Table 5
Total mass of TRUs to be produced and accumulated from operation of all units of NPPs (PWRs, PHWRs) planned to be deployed by 2029∗.
Nuclide
Half-life (y)
Total mass of TRUs (g) as of
Percentage of added mass for the period (%)
2016
2089
2109
2016 to 2089
2016 to 2109
2089 to 2109
241Am
4.32
E
+
02
3.79
E
+
05
1.70
E
+
06
2.39
E
+
06
349%
534%
41%
A
m
242
m
1.41
E
+
02
8.54
E
+
03
4.02
E
+
04
5.65
E
+
04
371%
565%
41%
243Am
7.37
E
+
03
1.31
E
+
06
1.26
E
+
07
1.72
E
+
07
862%
1220%
37%
242Cm
1.63
E
+
02
1.48
E
+
05
8.86
E
+
05
1.23
E
+
06
500%
737%
39%
244Cm
1.81
E
+
01
4.92
E
+
05
7.90
E
+
06
1.07
E
+
07
1506%
2080%
36%
237Np
2.14
E
+
06
5.73
E
+
06
2.43
E
+
07
3.43
E
+
07
324%
502%
42%
238Pu
8.77
E
+
01
2.19
E
+
06
1.24
E
+
07
1.73
E
+
07
466%
692%
40%
239Pu
2.41
E
+
04
5.52
E
+
07
1.84
E
+
08
2.65
E
+
08
233%
383%
45%
240Pu
6.56
E
+
03
2.61
E
+
07
9.59
E
+
07
1.37
E
+
08
267%
428%
44%
241Pu
1.43
E
+
01
1.22
E
+
07
5.47
E
+
07
7.70
E
+
07
348%
534%
42%
242Pu
3.73
E
+
05
5.53
E
+
06
3.62
E
+
07
5.01
E
+
07
553%
809%
39%
Total
1.09
E
+
08
4.30
E
+
08
6.16
E
+
08
385%
583%
41%
R
e
s
u
l
t
s
∗ for the year of 2089 represent the scenario where continued operation of 36 units of NPPs is not assumed, and those for the year of 2109 are for the scenario where continued operation of all NPPs except for Kori Unit 1 is taken into account.The continued operation of NPPs for up to an additional twenty years may increase the mass of each TRU nuclide by 41% in average. The increment of total inventory of TRUs produced from operation of NPPs for their design lifetimes or for longer continued operation turns out to be about 385% or 583% in average compared to the inventory as of March 2016.However, there might be a few reasons for the partially higher increment of specific TRUs such asAm243 and Cm244. In order to find the reason of the partially higher increase of Am243 and Cm244, the fraction of each TRU nuclide from different types of Korean NPPs (e.g., APR-1400, 1000 MWe PWR, and PHWR) was calculated and compared. As a result, it turns out that the fractions of Am243 and Cm244 from APR-1400 and APR+ NPPs are 2.2 and 3.75 times higher than those from 1000 MWe PWR as shown in Table 6. Secondly, specifically in case of Am243, the higher increment may be ascribed to the higher burnup of 60 GWD/MTHM for APR-1400 and APR+, since the production of Am243 increases exponentially with burnup [38].Table 6
Fractions of243Am and 244Cm generated from different types of Korean NPPs.
Reactor
Radionuclide
243Am
244Cm
PHWR
4.066
E
-
04
3.742
E
-
05
1000 MWe PWR
1.977
E
-
02
8.169
E
-
03
APR-1400
4.371
E
-
02
3.068
E
-
02
APR+
4.371
E
-
02
3.068
E
-
02


### 3.2. Estimation of Nominal Radiological Risks

Figure3 shows the time-dependent nominal radiotoxicity index (in Sv/g) for the total inventory of TRUs in SNF to be generated from all thirty-six units of NPPs without continued operation, which was calculated by (2) and (3) using the values of parameters in Table 5. Figure 3 also shows the general trend of time-dependent decreasing of radiotoxicity index and dominant TRU nuclides along with elapsed time from the year of 2089, in which the last NPP’s initial lifetime will be ended. During the first sixteen years, the total radiotoxicity index is controlled by Cm244, and then it is controlled by Pu238 until 250 years from its initial decay. Subsequently, the most important TRU nuclides are Pu240 until 8,200 years and Pu239 until 260,000 years, and then Pu242 and 237Np dominate the radiotoxicity index subsequently for relative comparison.Figure 3
Nominal radiotoxicity for ingestion of TRUs in SNF from NPPs in comparison with natural uranium along with elapsed time from 2089 without consideration of the possibility of continued operation.The relative ingestion radiotoxicity index of natural uranium is also plotted. The ingestion radiotoxicity index of the natural uranium was calculated from the specific activity (25,280 Bq/g) and ingestion dose coefficient for adult (31.7 mSv/g) of natural uranium [39]. It can be said that the radiotoxicity index of TRUs in total inventory of SNF will decrease down to the level of the natural uranium only after around 200,000-year-long radioactive decay. The shape of curves and time-dependent decreasing trend of the sum of the total radiotoxicity indices of TRUs in Figure 3 conform to those reported in other studies including textbooks dealing with the toxicity of SNF discharged from nuclear reactors, which demonstrates the feasibility of the calculation conducted and the results obtained in this study [29, 30].


### 3.3. Establishment of Strategic Scenarios to Transmute TRUs by SFRs

It was assumed that all TRUs present in SNF from all units of NPPs are to be transmuted in the SFRs by utilizing Pyro-SFR fuel cycle scenarios. In order to formulate the quantified transmutation schemes for TRUs with the incorporation of Pyro-SFR, basic scenarios in Table2 have been expanded as shown in Table 7, which shows the minimum number of SFRs to be required for each scenario along with the duration of commercialization of SFRs. As described above, the deployment of APR-1400 and APR+ by 2029 and SFRs from 2028 to their design or extended lifetime was assumed based upon the official national plans promulgated by the Korean government [2, 4]. However, additional NPPs (PWRs and PHWRs) and/or SFRs may be deployed thereafter beyond the time frame covered in the above national plans, which was not taken into account in this study because long-term forecast without sound basis may cause very high uncertainties and is not compatible with the main objective of this study.Table 7
Strategic scenarios for transmutation of TRUs.
Case I
Scenario SC-1
Scenario SC-2
Number of PWRs
32
32
Number of PHWRs
4
4
Deployment period of PWRs and PHWRs
1978–2029 (51 years)
1978–2029 (51 years)
MAs/Pu generated (MT)
47.38/383.08
66.14/549.43
Case II
Scenario SC-3
Scenario SC-4
MAs/TRUs generated in SC-1
47.38/430.47
47.38/430.47
Minimum number of SFRs needed
14
24
Deployment period of SFRs
2028–2049 (21 years)
2028–2066 (38 years)
Case III
Scenario SC-5
Scenario SC-6
MAs/TRUs generated in SC-2
66.14/615.57
66.14/615.57
Minimum number of SFRs needed
20
34
Deployment period of SFRs
2028–2059 (31 years)
2028–2083 (55 years)
Case IV
Scenario SC-7
Scenario SC-8
MAs/TRUs generated in SC-2
66.14/615.57
66.14/615.57
Minimum number of SFRs needed
15
25
Deployment period of SFRs
2028–2051 (23 years)
2028–2068 (40 years)
MT: metric ton; MAs: minor actinides; Pu: plutonium.Deployment rate of SFRs directly affects the elements of modeled transmutation scenarios such as the number of SFRs needed, the transmutation rate, and the target year of full transmutation of TRUs. In the case of PWRs and PHWRs, the deployment rate in average was calculated from the historical rate of commercialization of NPPs in Korea and the government’s future deployment plan for new reactors as announced. Totally, thirty-six units of NPPs have been and will be deployed from the first commercial operation of Kori Unit 1 in 1978 till the commercialization of the thirty-sixth reactor in 2029. That is, the average deployment rate of NPPs in Korea is 1.44 years (i.e., 17 months) per reactor. In case of SFR deployment in scenarios SC-3 to SC-8, however, it was assumed that each unit of SFR will be deployed every 1.67 years (i.e., 20 months) after the commercialization of the first SFR in 2028 in order to transmute all the inventory of TRUs generated from the operation of all thirty-six NPPs to be installed by 2029. As the SFR will be the first-of-a-kind (FOAK) reactor to be deployed in Korea, the average deployment rate of SFR was proposed to be 15% longer than the deployment rate of NPPs (i.e., PWRs and PHWRs) in this study.It is shown that at least fourteen to thirty-four units of SFRs should be used for full transmutation of TRUs from thirty-six units of NPPs, which mainly depends upon the design parameters (e.g., CR) of SFR, life extension of nuclear reactors, and so forth. It is noted that the SFR design with lower CR (0.46) such as in scenarios SC-3, SC-5, and SC-7 requires a smaller number of SFRs compared to scenarios SC-4, SC-6, and SC-8 which burn less TRUs per cycle due to higher CR (0.6). Therefore, more units of SFRs are needed and thus longer time duration of transmutation is required for scenarios SC-4, SC-6, and SC-8 than SC-3, SC-5, and SC-7 as shown in Table7.Some investigators have reported different numbers of SFRs (i.e., minimum of 29 to 45 or more) to be deployed in Korea to transmute TRUs based upon their own assumptions, in which two types of SFRs (i.e., break-even reactors with CR of no more than 1 and burners with CR of 0.61 to 0.70) were assumed [8, 13, 18]. In this study, we have considered two types of SFRs as burners (CR of 0.46 and 0.6) as one of the primary objectives of this study is to simulate the full-scale transmutation of TRUs by deploying SFRs with a minimum of 21-year and maximum of 55-year-long strategic planning as shown in Table 7.Figures4 and 5 show that TRUs generated from scenario SC-1 (i.e., operation of NPPs for design lifetimes) can be fully transmuted by the years of 2109 to 2126 with SC-3 and SC-4, respectively, and TRUs from SC-2 (i.e., extended operation of NPPs up to twenty years) by the years of 2119, 2143, 2133, and 2148 with SC-5, SC-6, SC-7, and SC-8, respectively, by the use of the minimum number of SFRs as shown in Table 7.Figure 4
Prospective reduction of mass of TRUs inventory depending upon two different scenarios in which PWRs and PHWRs are operated for design lifetimes.Figure 5
Prospective reduction of mass of TRUs inventory depending upon four different scenarios in which life extension of PWRs, PHWRs, and SFRs is allowed.The minimum number of SFRs needed for each scenario in Table7 was calculated by the use of the following equation:(5)NSFR=ATRU-NFCSSCTRU×OPRt,where ATRU-NFCSS is the amount of TRUs estimated by NFCSS (MTHM), CTRU is the consumption rate of TRUs per reactor-year (MTHM/reactor·y), and OPRt is the operational period of a reactor (y).As noticed, the scope of this study is to simulate the deployment of NPPs (i.e., PWRs and PHWRs) by the year of 2029 and SFRs from the year of 2028 until their operational or extended lifetime. Further deployment of NPPs and SFRs is not taken into account based on the 7th Basic Plan on Electricity Demand and Supply which includes the latest national policy and strategies to construct an additional eight units of APR-1400 and four units of APR+ by 2029 only. There is no specific plan to deploy NPPs after 2100 [2]. Since the first feed of nuclear fuel for SFRs will be manufactured from TRUs in the SNF produced from NPPs (i.e., PWRs and PHWRs), deployment of additional SFRs would not be assumed when the NPPs (i.e., origin of the nuclear fuel for SFR) are not to be present in the future [13, 31]. Moreover, the basic methodology proposed in this study would be applicable if the government plans to deploy new nuclear reactors in the future.


### 3.4. Estimation of Cost for Direct Disposal and Pyro-SFR Fuel Cycle Options

#### 3.4.1. Derivation of Process Costs Based upon Unit Costs from Existing Studies

In order to perform front- and back-end fuel cycle cost calculations, a variety of economic studies on nuclear fuel cycles were firstly reviewed and analyzed. It is intended in this study to consider the variabilities and uncertainties of unit cost data as much as possible by expanding the references of unit cost data and using a statistical manipulation. As a result, various domestic and overseas unit cost data available from reliable information resources such as official reports of competent international organizations and selected scientific papers published in international journals were collected as shown in Table8 [14–21, 35–37, 40–44]. All the unit cost data were normalized to the 2016 US dollar values.Table 8
Probability distribution function of nuclear fuel cycle process costs and reactor cost (based on 2016 USD).
Category
Probability distribution
Min
Max
Mean
Unit
References
Uranium∗
Triangular [37]
58
409
219
$/kgU
[14–18, 21, 35–37, 40–44]
Conversion
Uniform [12]
6
33
14
$/kgU
[14–18, 21, 35–37, 40–44]
Enrichment
Uniform [12]
262
411
481
$/SWU
[14–18, 21, 35–37, 40–44]
PWR fuel fabrication
Triangular [37]
281
422
346
$/kgHM
[14–18, 21, 35–37, 40–44]
PHWR fuel fabrication
Triangular [37]
60
186
152
$/kgHM
[17–21, 35, 36, 43]
UO2-pyroprocess
Triangular [37]
882
4,819
3,064
$/kgHM
[14–16, 18–20, 35, 36]
SFR-pyroprocess
Triangular [37]
1,392
5,692
3,786
$/kgHM
[14–16, 18–20, 35, 36]
SFR fuel fabrication
Triangular [37]
2,297
8,680
4,939
$/kgHM
[14–16, 18–20, 35–37, 40, 42]
PWR IS&T
Triangular [37]
133
925
480
$/kgHM
[14–21, 35–37, 40–43]
PHWR IS&T
Triangular [37]
64
701
393
$/kgHM
[17–21]
Pyroprocess HLW (storage)∗
Triangular [37]
124,561
231,612
199,692
$/m3
[15, 16, 19, 20]
LILW-SL disposal∗
Triangular [37]
3,465
4,170
3,818
$/m3
[15, 16, 37, 40]
LILW-LL disposal∗
Triangular [37]
9,240
11,121
9,867
$/m3
[15, 16, 37, 40]
PWR final disposal∗
Triangular [37]
521
2,245
1,107
$/kgHM
[14, 17–21, 37, 40–43]
PHWR final disposal∗
Triangular [37]
106
699
519
$/kgHM
[17–21]
Pyroprocess disposal∗
Triangular [37]
17,361
493,893
296,539
$/kgHM
[14, 15, 18–20, 37, 40, 41, 43]
PWR overnight∗
Triangular [37]
1,919
7,018
4,746
$/kWe
[17, 18, 37, 43]
PHWR overnight∗
Triangular [37]
1,903
3,268
2,587
$/kWe
[37]
SFR overnight∗
Triangular [37]
2,331
9,199
6,115
$/kWe
[17, 18, 40, 43]
IS&T: interim storage and transportation; HLW: high-level waste; LILW-SL: low intermediate level waste-short-lived; LILW-LL: low intermediate level waste-long-lived; Min: minimum; Max: maximum; kgU: kilogram uranium; SWU: separative work unit; KgHM: kilogram heavy metal; m3: cubic meter; USD: US dollar. Values∗ are adopted from different sources, normalized to 2016 USD, statistically analyzed, and presented in this table.In this study, first unit cost data is collected from different studies and statistically analyzed, and then individual process costs (as shown in Table8) were calculated by using the result of analysis as an input to (i) to (vii) from Table 12. The individual process costs were derived again by probabilistic calculation using a commercially available risk analysis software program called Crystal Ball™ utilizing Monte Carlo simulation, which randomly selects values for each input to the model from a distribution specified by the user. The calculation was done by use of (i) to (vii) from Table 12 after defining the parameters of probability distribution for the individual process costs of different nuclear fuel cycles. The other costs except for the individual process costs in Table 8 were derived from statistical analysis of reference unit costs. In accordance with the above methodology, the statistics of costs were calculated as shown in Table 9.Table 9
Descriptive statistics of process cost and reactor cost using 50,000 random samples with Monte Carlo method.
Category
Minimum
Maximum
Mean
Median
SD
CV
Uranium
58.16
407.27
228.89
226.88
71.46
0.31
Conversion
6.20
33.59
19.92
19.97
7.91
0.40
Enrichment
406.21
576.50
487.52
486.34
31.08
0.06
PWR fuel fabrication
284.63
425.83
352.40
351.10
29.04
0.08
PHWR fuel fabrication
63.77
188.97
134.76
137.84
26.48
0.20
UO2-pyroprocess
990.05
5,147.95
3,063.97
3,062.27
809.89
0.26
SFR-pyroprocess
1,514.36
5,963.69
3,765.25
3,774.47
879.01
0.23
SFR fuel fabrication
2,322.11
8,682.88
5,311.27
5,225.73
1,315.30
0.25
PWR IS&T
135.35
923.51
513.05
505.19
161.88
0.32
PHWR IS&T
65.51
699.21
385.24
386.78
130.25
0.34
Pyroprocess HLW (storage)
124,855.22
231,538.87
185,416.02
188,057.06
22,407.71
0.12
LILW-SL disposal
3,467.53
4,166.87
3,817.85
3,817.21
144.40
0.04
LILW-LL disposal
9,246.08
11,119.19
10,074.75
10,033.59
391.76
0.04
PWR final disposal
523.49
2,244.14
1,292.74
1,254.76
359.15
0.28
PHWR final disposal
296.62
698.04
503.64
507.00
83.10
0.16
Pyroprocess disposal
17,870.38
492,381.02
269,486.28
274,929.70
97,445.86
0.36
PWR overnight
1,907.61
7,027.80
4,758.43
4,869.87
1,067.17
0.22
PHWR overnight
105.46
1,896.52
1,197.88
1,258.74
393.91
0.33
SFR overnight
2,321.49
9,196.44
6,107.57
6,254.42
1,438.34
0.24
SD: standard deviation; CV: coefficient of variability.All∗ units are the same as in Table 8 for each item.Precision of the cost values can be analyzed by using the data of coefficient of variability (CV) given in Table9, which compares the variability of cost values relative to the mean or in other words precision of cost values. It is reportedly known that a parameter having a higher value of CV (i.e., dispersion around the mean is higher) is considered to be less precise. The values derived from Crystal Ball simulation can be said to be acceptable, since all values of CV in Table 9 range from 0 to 1 which are typically known to be precise enough [45].Three types of probability distributions, uniform, triangular, and normal distributions, which are typically used for cases where limited amount of sample data is available, as shown in Table8, were used for each cost element in order to quantify the uncertainties in estimation of the costs. The probability distribution of each cost in Table 8 was adopted from studies on economic analysis of nuclear fuel cycle [12, 37].


#### 3.4.2. Calculation of Fuel Cycle Costs

Figure6 shows the results of probabilistic calculation of the fuel cycle costs (FCCs) for selected fuel cycle options. With the assumption of probability distribution for each process cost element as stated in Table 8, a series of Monte Carlo simulations using Crystal Ball software were carried out for 50,000 samples to address the inherent uncertainties of the estimated cost. As a result of the simulation, the mean values of FCCs for PWR (direct disposal), PHWR (direct disposal), Pyro-SFR-1 (CR = 0.46), and Pyro-SFR-2 (CR = 0.6) were calculated basically by using (viii) to (xiv) from Table 12 to be 8.174 mills/kWh, 22.114 mills/kWh, 6.065 mills/kWh, and 11.310 mills/kWh, respectively.Figure 6
Probabilistic distribution of fuel cycle cost (FCC).As shown in the statistics of Figure6, the FCC for Pyro-SFR-1 (CR = 0.46) is found to be the most economical fuel cycle option followed by PWR (direct disposal), Pyro-SFR-2 (CR = 0.6), and PHWR (direct disposal). Difference between the FCCs of Pyro-SFR-1 and Pyro-SFR-2 mainly comes from the difference of the values of CR and burnups of SFRs between the two fuel cycles as shown in Table 3. As higher burnup generates more energy per unit mass of fuel; the mass of fuel required for SFR-2 is more than (almost double) that for SFR-1. Accordingly, the FCC in $/kWh for Pyro-SFR-1 turns out to be almost half that for Pyro-SFR-2 due to lower CR and higher burnup [13, 35, 46]. As can be seen from Figure 6, the FCC distribution of PHWR is wider than other fuel cycles and the distribution of Pyro-SFR-1 is narrower than others. It is noted that the peakedness and flatness of a distribution for PWR and Pyro-SFR-1 fuel cycles which resulted in Figure 6 are comparable with previous studies reported [14].


#### 3.4.3. Calculation of Scenario Cost

The next step in economic analysis is to estimate the scenario-based cost. As discussed in Tables2 and 7, four cases each consisting of two scenarios are analyzed and presented in Table 10, where the overall scenario cost including overnight cost, fuel cost, operation and management (O&M) cost, and decommissioning and decontamination (D&D) cost for each scenario was calculated by considering the mean value from Table 9. Table 10 shows the breakdown of all the cost elements for two direct disposal and six Pyro-SFR based fuel cycle scenarios. It is noted that the O&M cost and D&D cost are assumed to be calculated as 4% and 8% of overnight cost of reactors in each scenario in accordance with OECD/NEA studies [37]. In case of scenarios SC-1 and SC-2, the most affecting cost elements are PWR overnight cost followed by PWR fuel, PWR SNF disposal, PWR D&D, PHWR fuel cost, and others. The potential of continued operation of NPPs (PWRs and PHWRs) in scenario SC-2 up to an additional twenty years increases the total cost by 20.51%. However, the benefit of additional electricity generation to be obtained from continued operation of NPPs (PWRs and PHWRs) increases by 40%.Table 10
Overall scenario cost (unit: M$ based on 2016 USD).
Case I
SC-1
SC-2
Number of PWRs
32
32
Number of PHWRs
4
4
PWR overnight cost
171,955
171,955
PHWR overnight cost
3,329
3,329
PWR O&M cost
6,878
9,604∗
PWR D&D cost
13,756
19,208∗
PHWR O&M cost
133
218∗
PHWR D&D cost
266
435∗
PWR SNF disposal
39,046
54,215
PHWR SNF disposal
5,799
9,497
PWR fuel cost∗∗
86,435
120,012
PHWR fuel cost∗∗
14,648
23,990
Total PWR cost
318,071
374,995
Total PHWR cost
24,175
37,470
Overall scenario cost
342,246
412,465
PWR electricity generation (TWh)
12,380
17,183
PHWR electricity generation (TWh)
672
1,099
Overall electricity generation (TWh)
13,052
18,282
Case II
SC-3
SC-4
Minimum number of SFRs needed
14
24
Operating lifetime of SFR (y)
60
60
SFR overnight cost
51,304
87,949
SFR O&M cost
2,052
3,518
SFR D&D cost
4,104
7,036
SFR fuel cost∗∗
24,402
77,920
Overall scenario cost
82,080
176,796
SFR electricity generation (TWh)
4,014
6,870
Case III
SC-5
SC-6
Minimum number of SFRs needed
20
34
Operating lifetime of SFR (y)
60
60
SFR overnight cost
73,291
124,595
SFR O&M cost
2,932
4,984
SFR D&D cost
5,863
9,968
SFR fuel cost∗∗
34,861
110,387
Overall scenario cost
117,257
250,461
SFR electricity generation (TWh)
5,734
9,732
Case IV
SC-7
SC-8
Minimum number of SFRs needed
15
25
Operating lifetime of SFR (y)
80
80
SFR overnight cost
54,968
91,614
SFR O&M cost
2,932
4,886
SFR D&D cost
5,863
9,772
SFR fuel cost∗∗
34,861
108,222
Overall scenario cost
98,865
214,896
SFR electricity generation (TWh)
5,734
9,541
O&M: operation and management; D&D: decommissioning and decontamination; TWh: terawatt hours.O∗&M and D&D costs in SC-2 are derived from SC-1 for 20 years of a more operational period. PWR∗∗/PHWR/SFR fuel cost represents the total cost of the fuel for the specified type of nuclear reactor.As far as Pyro-SFR scenarios are concerned, overnight cost followed by the fuel cost of SFRs in each scenario contributes most in the overall Pyro-SFR energy systems. From scenarios SC-3 to SC-8, it is noted that each scenario has advantages and disadvantages in terms of cost, electricity generation, and the minimum number of SFRs needed. For example, if it is decided to transmute all TRUs without extending the operational lifetime of PWRs and PHWRs, SC-3 and SC-4 can be adopted for short- and long-term transmutation of TRUs, respectively, considering the cost and electricity generation. The major difference between the two is that SC-3 requires a shorter time and a smaller number of SFRs, eventually thus almost twice economical as compared with SC-4. However, the electricity generation from SC-4 is 41.5% higher as compared with SC-3, which can be regarded as a long-term benefit. In Case III and Case IV, similar analysis can be applicable in terms of scenario cost, minimum number of SFRs needed, and electricity generation in each scenario.Scenarios SC-7 and SC-8 reflect the extended operational lifetime of 20 years for all SFRs in order to transmute all TRUs being generated from SC-2. Upon comparison of Case III scenarios with Case IV scenarios, we found out that the total electricity generation from SC-5 and SC-7 is almost the same but SC-7 is more economical compared with SC-5, as it transmutes the same amount of TRUs with fewer units of SFRs while producing the same amount of electricity. In case of scenarios SC-6 and SC-8, relative electricity benefits between the two differ by 1.97%, as SC-8 generates 98.03% electricity comparable to SC-6, but in terms of cost and transmutation of TRUs from SC-2, SC-6 is 1.2 times more expensive and requires 26.4% more SFRs as compared with SC-8.It is noted that Table10 should not be used for the direct comparison between direct disposal and Pyro-SFR scenarios because each of SC-1 and SC-2 is a complete nuclear energy system while Pyro-SFR scenarios are just part of the whole nuclear energy system. Pyro-SFR scenarios directly depend on PWR and PHWR fuel cycle because TRUs from SC-1 and SC-2 are the only source of fuel for Pyro-SFR fuel cycle scenarios [13, 31].


#### 3.4.4. Comparison of Direct Disposal and Closed Nuclear Energy System Cost

In order to compare the economic feasibilities of direct disposal and Pyro-SFR closed fuel cycle, the total scenario costs for Pyro-SFR fuel cycles in Table10 should be further extended by adding the cost of the front part of the fuel cycle (e.g., existing PWRs and PHWRs fuel cycles).For the optimized strategy of closed nuclear energy system, scenarios were selected from Table10 based on the minimum ratio of cost to electricity generation and maximum transmutation of TRUs with the minimum number of SFRs for maximum benefits. For example, scenario SC-2 is chosen as a representative direct disposal scenario because of its higher electricity generation with a smaller increase of cost for continued operation of NPPs (PWRs and PHWRs). Secondly, in order to close the nuclear fuel cycle, scenarios SC-7 and SC-8 were chosen from six Pyro-SFR scenarios because of the minimum number of SFRs to be deployed for the transmutation of larger amounts of TRUs from SC-2 with a lower ratio of cost to electricity generation and higher electricity generation compared with other Pyro-SFR scenarios.The nuclear energy system cost (i.e., the total costs including overnight cost, fuel cost, O&M cost, D&D cost, and SNF disposal cost, if any) for closed fuel cycle is calculated by the combination of scenarios (i.e., CFC-1 by combining SC-2 and SC-7 and CFC-2 by combining SC-2 and SC-8) as shown in Table11. Two of the most affecting factors (i.e., PWR overnight and fuel costs) in SC-2 and two of the most affecting factors in SC-7 and SC-8 (i.e., SFR overnight and fuel costs) consist of the most dominant cost elements in CFC-1 and CFC-2, respectively, as listed in Table 11. It can be noted that CFC-2 is 20.57% cheaper than CFC-1 with only 13.19% less electricity generation because a smaller number of SFRs are needed for CFC-2. From Table 11, we can see that both CFC-1 and CFC-2 can be utilized for different objectives. That is, CFC-2 can be chosen for fast transmutation of TRUs with the minimum number of SFRs. On the other hand, CFC-1 can be selected for extended transmutation of TRUs with a comparatively higher number of SFRs, which generates 13.19% more electricity.Table 11
Estimation of closed nuclear energy system costs (unit: M$ based on 2016 USD).
Parameters
CFC-1
CFC-2
Number of PWRs
31
31
Number of PHWRs
4
4
Minimum number of SFRs needed
25
15
SFR’s CR
0.6
0.46
Operating lifetime (PWR/PHWR/SFR)
60/50/80
60/50/80
SFR overnight cost
91,614
54,968
PWR overnight cost
171,955
171,955
PHWR overnight cost
3,329
3,329
SFR fuel cost
108,222
34,861
PWR fuel cost
120,012
120,012
PHWR fuel cost
23,990
23,990
SFR O&M cost
4,886
2,932
PWR O&M cost
9,604
9,604
PHWR O&M cost
218
218
SFR D&D cost
9,772
5,863
PWR D&D cost
19,208
19,208
PHWR D&D cost
435
435
Closed nuclear energy system cost
563,246
447,376
Electricity generation (TWh)
28,841
25,035
CFC: closed fuel cycle.Table 12
Modified set of equations to estimate the cost of nuclear fuel cycle based on equilibrium model.
Category
Equations
Individual process cost
Cost for conversion ($/kgU) (C(CON))
C
(
C
O
N
)
=
U
C
(
C
O
N
)
⋅
A
(
C
O
N
)
(i)
Cost for enrichment ($/SWU) (C(ENR))
C
(
E
N
R
)
=
U
C
(
S
W
U
)
⋅
A
(
N
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(ii)
Cost for PWR fuel fabrication ($/kgHM) (C(PWRFAB))
C
(
P
W
R
F
A
B
)
=
U
C
(
P
W
R
F
A
B
)
⋅
A
(
F
A
B
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(iii)
Cost for PHWR fuel fabrication ($/kgHM) (C(PHWRFAB))
C
(
P
H
W
R
F
A
B
)
=
U
C
(
P
H
W
R
F
A
B
)
⋅
A
(
F
A
B
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(iv)
Cost for pyroprocessing ($/kgHM) (C(PYRO))
C
(
P
Y
R
O
)
=
U
C
(
P
Y
R
O
)
⋅
A
(
R
E
C
)
+
U
D
(
L
I
-
L
L
)
⋅
A
D
(
L
I
-
L
L
)
+
U
D
(
H
L
W
)
⋅
A
D
(
H
L
W
)
(v)
Cost for SFR fuel fabrication ($/kgHM) (C(SFRFAB))
C
(
S
F
R
F
A
B
)
=
U
C
(
S
F
R
F
A
B
)
⋅
A
(
F
A
B
)
+
C
D
(
L
I
-
L
L
)
⋅
A
D
(
L
I
-
L
L
)
(vi)
Cost for storage and transport ($/kgHM) (C(STR))
C
(
S
T
R
)
=
U
C
(
S
)
⋅
A
(
S
)
+
U
C
(
T
R
)
⋅
A
(
T
R
)
(vii)
Total process cost
Total cost for PWR process ($/kgHM) (C(PWR)P)
C
(
P
W
R
)
P
=
C
(
C
O
N
)
+
C
(
E
N
R
)
+
C
(
P
W
R
F
A
B
)
+
C
(
S
T
R
)
+
C
D
(
S
N
F
)
∗
(viii)
Total cost for PHWR process ($/kgHM) (C(PHWR)P)
C
(
P
H
W
R
)
P
=
C
(
C
O
N
)
+
C
(
P
H
W
R
F
A
B
)
+
C
(
S
T
R
)
+
C
D
(
S
N
F
)
∗
(ix)
Total cost for Pyro-SFR process ($/kgHM) (CPyro-SFRP)
C
P
y
r
o
-
S
F
R
P
=
C
(
P
Y
R
O
)
+
C
(
S
F
R
F
A
B
)
+
C
(
S
T
R
)
(x)
Fuel cycle cost
PWR fuel cycle cost ($/kWh), (CF(PWR))
C
F
(
P
W
R
)
=
C
(
P
W
R
)
P
0.32
M
W
e
/
M
W
t
⋅
45
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xi)
PHWR fuel cycle cost ($/kWh) (CF(PHWR))
C
F
(
P
H
W
R
)
=
C
(
P
H
W
R
)
P
0.32
M
W
e
/
M
W
t
⋅
7.5
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xii)
Pyro-SFR fuel cycle cost ($/kWh), CR = 0.46 (CFPYRO-SFR,CR=0.46)
C
F
P
Y
R
O
-
S
F
R
,
C
R
=
0.46
=
C
P
y
r
o
-
S
F
R
P
0.394
M
W
e
/
M
W
t
⋅
217
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xiii)
Pyro-SFR fuel cycle cost ($/kWh), CR = 0.6 (CFPYRO-SFR,CR=0.6)
C
F
P
Y
R
O
-
S
F
R
,
C
R
=
0.6
=
C
P
y
r
o
-
S
F
R
P
0.394
M
W
e
/
M
W
t
⋅
116.3
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xiv)
C
D
(
S
N
F
)
∗: cost of disposing of spent nuclear fuel from NPPs (PWRs and PHWRs) =AD(SNF)⋅UD(SNF); UC(CON): unit cost of conversion; UC(SWU): unit cost of enrichment; UC(PWRFAB): unit cost of PWR fuel fabrication; UC(PHWRFAB): unit cost of PHWR fuel fabrication; UC(PYRO): unit cost of pyroprocessing; UC(SFRFAB): unit cost for SFR fuel fabrication; UC(S): unit cost of storage; UCTR: unit cost of transportation; UD(LI-SL): unit cost of disposing of low intermediate-short-lived waste; UD(LI-LL): unit cost of disposing of low intermediate-long-lived waste; UD(HLW): unit cost of disposing of high-level waste; UD(SNF): unit cost of disposing of spent nuclear fuel; A(CON): amount of uranium to be converted; A(N): amount for enrichment; A(FAB): amount of fuel to be fabricated; A(REC): amount of fuel to be recycled; A(S): amount of fuel to be stored; A(TR): amount of fuel to be transported; AD(LI-SL): amount of disposing of low intermediate-short-lived waste; AD(LI-LL): amount of disposing of low intermediate-long-lived waste; AD(HLW): amount of disposing of high-level waste; AD(SNF): amount of disposing of spent nuclear fuel; C(PWR)P: total cost of PWR fuel cycle; C(PHWR)P: total cost of PHWR fuel cycle; C(Pyro-SFR)P: total cost of Pyro-SFR fuel cycle; CF(PWR): fuel cycle cost of PWR fuel cycle; CF(PHWR): fuel cycle cost of PHWR fuel cycle; CF(Pyro-SFR)CR=0.46: fuel cycle cost of Pyro-SFRCR=0.46 fuel cycle; CF(Pyro-SFR)CR=0.6: fuel cycle cost of Pyro-SFRCR=0.6 fuel cycle.Figure7 shows the statistics from the Monte Carlo simulation with the assumption that each parameter of direct disposal and closed nuclear energy system has a triangular distribution. A series of Monte Carlo simulations were carried out using 50,000 samples, and the total generation costs for SC-1, SC-2, CFC-1, and CFC-2 are calculated to be 24.497 ± 2.995 (1σ), 21.382 ± 2.318, 19.220 ± 1.817, and 17.620 ± 1.785 $/kWh, respectively. Scenarios SC-1 and SC-2, which are a combination of PWR and PHWR nuclear energy systems, are being considered as a single integrated direct disposal nuclear energy system; hence, the cost incurred at any point in SC-1 and SC-2 should be normalized with the electricity produced throughout SC-1 and SC-2. Similarly, fuel cycle with recycling of TRUs is considered as a single integrated technology; therefore, the cost incurred at any point in the CFC-1 and CFC-2 is normalized across the electricity produced throughout the whole closed fuel cycle [35].Figure 7
Probabilistic estimation of the total generation cost for direct disposal and closed nuclear energy systems using 50,000 samples.


#### 3.4.5. Break-Even SFR Overnight Cost

In order to determine a specific condition under which the Pyro-SFR closed nuclear energy system shows positive economic feasibility over direct disposal option, a break-even point of SFR overnight cost is estimated. As shown in Figure8, the break-even SFR overnight cost per reactor for CFC-1 and CFC-2 is calculated to be M$ 2,570 and M$ 3,450, respectively. It can be said that the closed nuclear energy system CFC-1 or CFC-2 is more economically feasible compared to direct disposal scenario SC-2 if SFR overnight cost falls below the break-even point as calculated in the figure.Figure 8
Relation between the break-even points of unit SFR overnight cost with CFC-1, CFC-2, and SC-2.


#### 3.4.6. Sensitivity Analysis for Closed Fuel Cycles

Sensitivity analysis has been carried out to analyze the cost elements in closed fuel cycle that may affect the nuclear energy system cost by using Crystal Ball software. Crystal Ball computes the sensitivity by computing rank correlation coefficients. Correlation coefficients measure the strength of the linear relationship among the parameters in CFC-1 and CFC-2. A parameter having a higher correlation coefficient value affects more the total cost of closed nuclear energy system.Figure9 shows that the five most affecting factors in CFC-1 and CFC-2 are the PWR overnight cost, SFR overnight cost, SFR fuel cost, PWR fuel cost, and PHWR fuel cost. As mentioned, it is noted that, even though sensitivity for direct disposal energy system is not conducted, the relative sensitivity of cost elements in SC-1 and SC-2 can be calculated by taking into account the cost parameters related to PWR and PHWRs only from Figure 9.Figure 9
Sensitivity of cost elements in closed fuel cycle nuclear energy systems: (a) CFC-1 and (b) CFC-2.
(a)
(b)


## 3.1. Estimation of Total Inventory of SNF and TRUs

As shown in Table4, the total amount of SNF generated from twenty-four units of operating NPPs as of March 2016 was calculated to be 14,511 metric tons of heavy metal (MTHM) by the NFCSS and the information given in Table 1. The result is quite comparable to the officially reported total inventory of SNF in terms of mass (i.e., 14,608 MTU) accumulated as of March 2016 within the relative error of less than 0.7 percent [1].Table 4
Total amount of SNF to be generated from operation of all units of PWRs and PHWRs planned to be deployed by 2029 per reactor site.
Site
Amount of SNF (MTHM)
As of March 2016
With operation for initial design lifetime (2089)∗
With continued operation for an additional 20 years (2109)∗
This study
[1] (MTU)
Kori (PWRs)
2,201
2,294
11,905
16,282
Hanul (PWRs)
2,049
2,043
9,716
13,697
Hanbit (PWRs)
2,391
2,403
4,502
6,753
Shin-Wolsong (PWRs)
65
54
1,203
1,804
Wolsong (PHWRs)
7,805
7,815
11,514
18,858
Cheonji (PWRs)
—
—
2,878
3,837
Total
14,511
14,608
41,718
61,232
R
e
s
u
l
t
s
∗ for the year of 2089 represent the scenario where continued operation of 36 units of NPPs is not assumed, and those for the year of 2109 are for the scenario where continued operation of all NPPs except for Kori Unit 1 is taken into account. In addition, the contribution of fission products in the spent nuclear fuel is not included in this table.In addition, the overall inventory of SNF to be produced from thirty-six units of NPPs during their initial design lifetimes only and additional continued operation periods (except for Kori Unit 1) were estimated to be 41,718 and 61,232 MTHM, respectively. That is, about 2.9 to 4.2 times more SNF in mass than the present inventory as of March 2016 will be accumulated if an additional eight units of APR-1400 and four units of APR+ type PWRs are deployed by 2029 as officially planned. It is also noted that the potential of continued operation of NPPs up to an additional twenty years may affect the total national inventory of SNF by a factor of 1.47 (≈61,232/41,718).Table5 shows the estimated mass (in grams) of each TRU nuclide which already exists in the total inventory of SNF generated from NPPs as of 2016 and the SNF to be further generated from all NPPs in operation and under construction or planning. It is noted that the mass of fission products is not included in Table 5, since this study mainly focuses on the radiotoxicity of the SNF in the long term as addressed in Section 2.2.Table 5
Total mass of TRUs to be produced and accumulated from operation of all units of NPPs (PWRs, PHWRs) planned to be deployed by 2029∗.
Nuclide
Half-life (y)
Total mass of TRUs (g) as of
Percentage of added mass for the period (%)
2016
2089
2109
2016 to 2089
2016 to 2109
2089 to 2109
241Am
4.32
E
+
02
3.79
E
+
05
1.70
E
+
06
2.39
E
+
06
349%
534%
41%
A
m
242
m
1.41
E
+
02
8.54
E
+
03
4.02
E
+
04
5.65
E
+
04
371%
565%
41%
243Am
7.37
E
+
03
1.31
E
+
06
1.26
E
+
07
1.72
E
+
07
862%
1220%
37%
242Cm
1.63
E
+
02
1.48
E
+
05
8.86
E
+
05
1.23
E
+
06
500%
737%
39%
244Cm
1.81
E
+
01
4.92
E
+
05
7.90
E
+
06
1.07
E
+
07
1506%
2080%
36%
237Np
2.14
E
+
06
5.73
E
+
06
2.43
E
+
07
3.43
E
+
07
324%
502%
42%
238Pu
8.77
E
+
01
2.19
E
+
06
1.24
E
+
07
1.73
E
+
07
466%
692%
40%
239Pu
2.41
E
+
04
5.52
E
+
07
1.84
E
+
08
2.65
E
+
08
233%
383%
45%
240Pu
6.56
E
+
03
2.61
E
+
07
9.59
E
+
07
1.37
E
+
08
267%
428%
44%
241Pu
1.43
E
+
01
1.22
E
+
07
5.47
E
+
07
7.70
E
+
07
348%
534%
42%
242Pu
3.73
E
+
05
5.53
E
+
06
3.62
E
+
07
5.01
E
+
07
553%
809%
39%
Total
1.09
E
+
08
4.30
E
+
08
6.16
E
+
08
385%
583%
41%
R
e
s
u
l
t
s
∗ for the year of 2089 represent the scenario where continued operation of 36 units of NPPs is not assumed, and those for the year of 2109 are for the scenario where continued operation of all NPPs except for Kori Unit 1 is taken into account.The continued operation of NPPs for up to an additional twenty years may increase the mass of each TRU nuclide by 41% in average. The increment of total inventory of TRUs produced from operation of NPPs for their design lifetimes or for longer continued operation turns out to be about 385% or 583% in average compared to the inventory as of March 2016.However, there might be a few reasons for the partially higher increment of specific TRUs such asAm243 and Cm244. In order to find the reason of the partially higher increase of Am243 and Cm244, the fraction of each TRU nuclide from different types of Korean NPPs (e.g., APR-1400, 1000 MWe PWR, and PHWR) was calculated and compared. As a result, it turns out that the fractions of Am243 and Cm244 from APR-1400 and APR+ NPPs are 2.2 and 3.75 times higher than those from 1000 MWe PWR as shown in Table 6. Secondly, specifically in case of Am243, the higher increment may be ascribed to the higher burnup of 60 GWD/MTHM for APR-1400 and APR+, since the production of Am243 increases exponentially with burnup [38].Table 6
Fractions of243Am and 244Cm generated from different types of Korean NPPs.
Reactor
Radionuclide
243Am
244Cm
PHWR
4.066
E
-
04
3.742
E
-
05
1000 MWe PWR
1.977
E
-
02
8.169
E
-
03
APR-1400
4.371
E
-
02
3.068
E
-
02
APR+
4.371
E
-
02
3.068
E
-
02


## 3.2. Estimation of Nominal Radiological Risks

Figure3 shows the time-dependent nominal radiotoxicity index (in Sv/g) for the total inventory of TRUs in SNF to be generated from all thirty-six units of NPPs without continued operation, which was calculated by (2) and (3) using the values of parameters in Table 5. Figure 3 also shows the general trend of time-dependent decreasing of radiotoxicity index and dominant TRU nuclides along with elapsed time from the year of 2089, in which the last NPP’s initial lifetime will be ended. During the first sixteen years, the total radiotoxicity index is controlled by Cm244, and then it is controlled by Pu238 until 250 years from its initial decay. Subsequently, the most important TRU nuclides are Pu240 until 8,200 years and Pu239 until 260,000 years, and then Pu242 and 237Np dominate the radiotoxicity index subsequently for relative comparison.Figure 3
Nominal radiotoxicity for ingestion of TRUs in SNF from NPPs in comparison with natural uranium along with elapsed time from 2089 without consideration of the possibility of continued operation.The relative ingestion radiotoxicity index of natural uranium is also plotted. The ingestion radiotoxicity index of the natural uranium was calculated from the specific activity (25,280 Bq/g) and ingestion dose coefficient for adult (31.7 mSv/g) of natural uranium [39]. It can be said that the radiotoxicity index of TRUs in total inventory of SNF will decrease down to the level of the natural uranium only after around 200,000-year-long radioactive decay. The shape of curves and time-dependent decreasing trend of the sum of the total radiotoxicity indices of TRUs in Figure 3 conform to those reported in other studies including textbooks dealing with the toxicity of SNF discharged from nuclear reactors, which demonstrates the feasibility of the calculation conducted and the results obtained in this study [29, 30].


## 3.3. Establishment of Strategic Scenarios to Transmute TRUs by SFRs

It was assumed that all TRUs present in SNF from all units of NPPs are to be transmuted in the SFRs by utilizing Pyro-SFR fuel cycle scenarios. In order to formulate the quantified transmutation schemes for TRUs with the incorporation of Pyro-SFR, basic scenarios in Table2 have been expanded as shown in Table 7, which shows the minimum number of SFRs to be required for each scenario along with the duration of commercialization of SFRs. As described above, the deployment of APR-1400 and APR+ by 2029 and SFRs from 2028 to their design or extended lifetime was assumed based upon the official national plans promulgated by the Korean government [2, 4]. However, additional NPPs (PWRs and PHWRs) and/or SFRs may be deployed thereafter beyond the time frame covered in the above national plans, which was not taken into account in this study because long-term forecast without sound basis may cause very high uncertainties and is not compatible with the main objective of this study.Table 7
Strategic scenarios for transmutation of TRUs.
Case I
Scenario SC-1
Scenario SC-2
Number of PWRs
32
32
Number of PHWRs
4
4
Deployment period of PWRs and PHWRs
1978–2029 (51 years)
1978–2029 (51 years)
MAs/Pu generated (MT)
47.38/383.08
66.14/549.43
Case II
Scenario SC-3
Scenario SC-4
MAs/TRUs generated in SC-1
47.38/430.47
47.38/430.47
Minimum number of SFRs needed
14
24
Deployment period of SFRs
2028–2049 (21 years)
2028–2066 (38 years)
Case III
Scenario SC-5
Scenario SC-6
MAs/TRUs generated in SC-2
66.14/615.57
66.14/615.57
Minimum number of SFRs needed
20
34
Deployment period of SFRs
2028–2059 (31 years)
2028–2083 (55 years)
Case IV
Scenario SC-7
Scenario SC-8
MAs/TRUs generated in SC-2
66.14/615.57
66.14/615.57
Minimum number of SFRs needed
15
25
Deployment period of SFRs
2028–2051 (23 years)
2028–2068 (40 years)
MT: metric ton; MAs: minor actinides; Pu: plutonium.Deployment rate of SFRs directly affects the elements of modeled transmutation scenarios such as the number of SFRs needed, the transmutation rate, and the target year of full transmutation of TRUs. In the case of PWRs and PHWRs, the deployment rate in average was calculated from the historical rate of commercialization of NPPs in Korea and the government’s future deployment plan for new reactors as announced. Totally, thirty-six units of NPPs have been and will be deployed from the first commercial operation of Kori Unit 1 in 1978 till the commercialization of the thirty-sixth reactor in 2029. That is, the average deployment rate of NPPs in Korea is 1.44 years (i.e., 17 months) per reactor. In case of SFR deployment in scenarios SC-3 to SC-8, however, it was assumed that each unit of SFR will be deployed every 1.67 years (i.e., 20 months) after the commercialization of the first SFR in 2028 in order to transmute all the inventory of TRUs generated from the operation of all thirty-six NPPs to be installed by 2029. As the SFR will be the first-of-a-kind (FOAK) reactor to be deployed in Korea, the average deployment rate of SFR was proposed to be 15% longer than the deployment rate of NPPs (i.e., PWRs and PHWRs) in this study.It is shown that at least fourteen to thirty-four units of SFRs should be used for full transmutation of TRUs from thirty-six units of NPPs, which mainly depends upon the design parameters (e.g., CR) of SFR, life extension of nuclear reactors, and so forth. It is noted that the SFR design with lower CR (0.46) such as in scenarios SC-3, SC-5, and SC-7 requires a smaller number of SFRs compared to scenarios SC-4, SC-6, and SC-8 which burn less TRUs per cycle due to higher CR (0.6). Therefore, more units of SFRs are needed and thus longer time duration of transmutation is required for scenarios SC-4, SC-6, and SC-8 than SC-3, SC-5, and SC-7 as shown in Table7.Some investigators have reported different numbers of SFRs (i.e., minimum of 29 to 45 or more) to be deployed in Korea to transmute TRUs based upon their own assumptions, in which two types of SFRs (i.e., break-even reactors with CR of no more than 1 and burners with CR of 0.61 to 0.70) were assumed [8, 13, 18]. In this study, we have considered two types of SFRs as burners (CR of 0.46 and 0.6) as one of the primary objectives of this study is to simulate the full-scale transmutation of TRUs by deploying SFRs with a minimum of 21-year and maximum of 55-year-long strategic planning as shown in Table 7.Figures4 and 5 show that TRUs generated from scenario SC-1 (i.e., operation of NPPs for design lifetimes) can be fully transmuted by the years of 2109 to 2126 with SC-3 and SC-4, respectively, and TRUs from SC-2 (i.e., extended operation of NPPs up to twenty years) by the years of 2119, 2143, 2133, and 2148 with SC-5, SC-6, SC-7, and SC-8, respectively, by the use of the minimum number of SFRs as shown in Table 7.Figure 4
Prospective reduction of mass of TRUs inventory depending upon two different scenarios in which PWRs and PHWRs are operated for design lifetimes.Figure 5
Prospective reduction of mass of TRUs inventory depending upon four different scenarios in which life extension of PWRs, PHWRs, and SFRs is allowed.The minimum number of SFRs needed for each scenario in Table7 was calculated by the use of the following equation:(5)NSFR=ATRU-NFCSSCTRU×OPRt,where ATRU-NFCSS is the amount of TRUs estimated by NFCSS (MTHM), CTRU is the consumption rate of TRUs per reactor-year (MTHM/reactor·y), and OPRt is the operational period of a reactor (y).As noticed, the scope of this study is to simulate the deployment of NPPs (i.e., PWRs and PHWRs) by the year of 2029 and SFRs from the year of 2028 until their operational or extended lifetime. Further deployment of NPPs and SFRs is not taken into account based on the 7th Basic Plan on Electricity Demand and Supply which includes the latest national policy and strategies to construct an additional eight units of APR-1400 and four units of APR+ by 2029 only. There is no specific plan to deploy NPPs after 2100 [2]. Since the first feed of nuclear fuel for SFRs will be manufactured from TRUs in the SNF produced from NPPs (i.e., PWRs and PHWRs), deployment of additional SFRs would not be assumed when the NPPs (i.e., origin of the nuclear fuel for SFR) are not to be present in the future [13, 31]. Moreover, the basic methodology proposed in this study would be applicable if the government plans to deploy new nuclear reactors in the future.


## 3.4. Estimation of Cost for Direct Disposal and Pyro-SFR Fuel Cycle Options

### 3.4.1. Derivation of Process Costs Based upon Unit Costs from Existing Studies

In order to perform front- and back-end fuel cycle cost calculations, a variety of economic studies on nuclear fuel cycles were firstly reviewed and analyzed. It is intended in this study to consider the variabilities and uncertainties of unit cost data as much as possible by expanding the references of unit cost data and using a statistical manipulation. As a result, various domestic and overseas unit cost data available from reliable information resources such as official reports of competent international organizations and selected scientific papers published in international journals were collected as shown in Table8 [14–21, 35–37, 40–44]. All the unit cost data were normalized to the 2016 US dollar values.Table 8
Probability distribution function of nuclear fuel cycle process costs and reactor cost (based on 2016 USD).
Category
Probability distribution
Min
Max
Mean
Unit
References
Uranium∗
Triangular [37]
58
409
219
$/kgU
[14–18, 21, 35–37, 40–44]
Conversion
Uniform [12]
6
33
14
$/kgU
[14–18, 21, 35–37, 40–44]
Enrichment
Uniform [12]
262
411
481
$/SWU
[14–18, 21, 35–37, 40–44]
PWR fuel fabrication
Triangular [37]
281
422
346
$/kgHM
[14–18, 21, 35–37, 40–44]
PHWR fuel fabrication
Triangular [37]
60
186
152
$/kgHM
[17–21, 35, 36, 43]
UO2-pyroprocess
Triangular [37]
882
4,819
3,064
$/kgHM
[14–16, 18–20, 35, 36]
SFR-pyroprocess
Triangular [37]
1,392
5,692
3,786
$/kgHM
[14–16, 18–20, 35, 36]
SFR fuel fabrication
Triangular [37]
2,297
8,680
4,939
$/kgHM
[14–16, 18–20, 35–37, 40, 42]
PWR IS&T
Triangular [37]
133
925
480
$/kgHM
[14–21, 35–37, 40–43]
PHWR IS&T
Triangular [37]
64
701
393
$/kgHM
[17–21]
Pyroprocess HLW (storage)∗
Triangular [37]
124,561
231,612
199,692
$/m3
[15, 16, 19, 20]
LILW-SL disposal∗
Triangular [37]
3,465
4,170
3,818
$/m3
[15, 16, 37, 40]
LILW-LL disposal∗
Triangular [37]
9,240
11,121
9,867
$/m3
[15, 16, 37, 40]
PWR final disposal∗
Triangular [37]
521
2,245
1,107
$/kgHM
[14, 17–21, 37, 40–43]
PHWR final disposal∗
Triangular [37]
106
699
519
$/kgHM
[17–21]
Pyroprocess disposal∗
Triangular [37]
17,361
493,893
296,539
$/kgHM
[14, 15, 18–20, 37, 40, 41, 43]
PWR overnight∗
Triangular [37]
1,919
7,018
4,746
$/kWe
[17, 18, 37, 43]
PHWR overnight∗
Triangular [37]
1,903
3,268
2,587
$/kWe
[37]
SFR overnight∗
Triangular [37]
2,331
9,199
6,115
$/kWe
[17, 18, 40, 43]
IS&T: interim storage and transportation; HLW: high-level waste; LILW-SL: low intermediate level waste-short-lived; LILW-LL: low intermediate level waste-long-lived; Min: minimum; Max: maximum; kgU: kilogram uranium; SWU: separative work unit; KgHM: kilogram heavy metal; m3: cubic meter; USD: US dollar. Values∗ are adopted from different sources, normalized to 2016 USD, statistically analyzed, and presented in this table.In this study, first unit cost data is collected from different studies and statistically analyzed, and then individual process costs (as shown in Table8) were calculated by using the result of analysis as an input to (i) to (vii) from Table 12. The individual process costs were derived again by probabilistic calculation using a commercially available risk analysis software program called Crystal Ball™ utilizing Monte Carlo simulation, which randomly selects values for each input to the model from a distribution specified by the user. The calculation was done by use of (i) to (vii) from Table 12 after defining the parameters of probability distribution for the individual process costs of different nuclear fuel cycles. The other costs except for the individual process costs in Table 8 were derived from statistical analysis of reference unit costs. In accordance with the above methodology, the statistics of costs were calculated as shown in Table 9.Table 9
Descriptive statistics of process cost and reactor cost using 50,000 random samples with Monte Carlo method.
Category
Minimum
Maximum
Mean
Median
SD
CV
Uranium
58.16
407.27
228.89
226.88
71.46
0.31
Conversion
6.20
33.59
19.92
19.97
7.91
0.40
Enrichment
406.21
576.50
487.52
486.34
31.08
0.06
PWR fuel fabrication
284.63
425.83
352.40
351.10
29.04
0.08
PHWR fuel fabrication
63.77
188.97
134.76
137.84
26.48
0.20
UO2-pyroprocess
990.05
5,147.95
3,063.97
3,062.27
809.89
0.26
SFR-pyroprocess
1,514.36
5,963.69
3,765.25
3,774.47
879.01
0.23
SFR fuel fabrication
2,322.11
8,682.88
5,311.27
5,225.73
1,315.30
0.25
PWR IS&T
135.35
923.51
513.05
505.19
161.88
0.32
PHWR IS&T
65.51
699.21
385.24
386.78
130.25
0.34
Pyroprocess HLW (storage)
124,855.22
231,538.87
185,416.02
188,057.06
22,407.71
0.12
LILW-SL disposal
3,467.53
4,166.87
3,817.85
3,817.21
144.40
0.04
LILW-LL disposal
9,246.08
11,119.19
10,074.75
10,033.59
391.76
0.04
PWR final disposal
523.49
2,244.14
1,292.74
1,254.76
359.15
0.28
PHWR final disposal
296.62
698.04
503.64
507.00
83.10
0.16
Pyroprocess disposal
17,870.38
492,381.02
269,486.28
274,929.70
97,445.86
0.36
PWR overnight
1,907.61
7,027.80
4,758.43
4,869.87
1,067.17
0.22
PHWR overnight
105.46
1,896.52
1,197.88
1,258.74
393.91
0.33
SFR overnight
2,321.49
9,196.44
6,107.57
6,254.42
1,438.34
0.24
SD: standard deviation; CV: coefficient of variability.All∗ units are the same as in Table 8 for each item.Precision of the cost values can be analyzed by using the data of coefficient of variability (CV) given in Table9, which compares the variability of cost values relative to the mean or in other words precision of cost values. It is reportedly known that a parameter having a higher value of CV (i.e., dispersion around the mean is higher) is considered to be less precise. The values derived from Crystal Ball simulation can be said to be acceptable, since all values of CV in Table 9 range from 0 to 1 which are typically known to be precise enough [45].Three types of probability distributions, uniform, triangular, and normal distributions, which are typically used for cases where limited amount of sample data is available, as shown in Table8, were used for each cost element in order to quantify the uncertainties in estimation of the costs. The probability distribution of each cost in Table 8 was adopted from studies on economic analysis of nuclear fuel cycle [12, 37].


### 3.4.2. Calculation of Fuel Cycle Costs

Figure6 shows the results of probabilistic calculation of the fuel cycle costs (FCCs) for selected fuel cycle options. With the assumption of probability distribution for each process cost element as stated in Table 8, a series of Monte Carlo simulations using Crystal Ball software were carried out for 50,000 samples to address the inherent uncertainties of the estimated cost. As a result of the simulation, the mean values of FCCs for PWR (direct disposal), PHWR (direct disposal), Pyro-SFR-1 (CR = 0.46), and Pyro-SFR-2 (CR = 0.6) were calculated basically by using (viii) to (xiv) from Table 12 to be 8.174 mills/kWh, 22.114 mills/kWh, 6.065 mills/kWh, and 11.310 mills/kWh, respectively.Figure 6
Probabilistic distribution of fuel cycle cost (FCC).As shown in the statistics of Figure6, the FCC for Pyro-SFR-1 (CR = 0.46) is found to be the most economical fuel cycle option followed by PWR (direct disposal), Pyro-SFR-2 (CR = 0.6), and PHWR (direct disposal). Difference between the FCCs of Pyro-SFR-1 and Pyro-SFR-2 mainly comes from the difference of the values of CR and burnups of SFRs between the two fuel cycles as shown in Table 3. As higher burnup generates more energy per unit mass of fuel; the mass of fuel required for SFR-2 is more than (almost double) that for SFR-1. Accordingly, the FCC in $/kWh for Pyro-SFR-1 turns out to be almost half that for Pyro-SFR-2 due to lower CR and higher burnup [13, 35, 46]. As can be seen from Figure 6, the FCC distribution of PHWR is wider than other fuel cycles and the distribution of Pyro-SFR-1 is narrower than others. It is noted that the peakedness and flatness of a distribution for PWR and Pyro-SFR-1 fuel cycles which resulted in Figure 6 are comparable with previous studies reported [14].


### 3.4.3. Calculation of Scenario Cost

The next step in economic analysis is to estimate the scenario-based cost. As discussed in Tables2 and 7, four cases each consisting of two scenarios are analyzed and presented in Table 10, where the overall scenario cost including overnight cost, fuel cost, operation and management (O&M) cost, and decommissioning and decontamination (D&D) cost for each scenario was calculated by considering the mean value from Table 9. Table 10 shows the breakdown of all the cost elements for two direct disposal and six Pyro-SFR based fuel cycle scenarios. It is noted that the O&M cost and D&D cost are assumed to be calculated as 4% and 8% of overnight cost of reactors in each scenario in accordance with OECD/NEA studies [37]. In case of scenarios SC-1 and SC-2, the most affecting cost elements are PWR overnight cost followed by PWR fuel, PWR SNF disposal, PWR D&D, PHWR fuel cost, and others. The potential of continued operation of NPPs (PWRs and PHWRs) in scenario SC-2 up to an additional twenty years increases the total cost by 20.51%. However, the benefit of additional electricity generation to be obtained from continued operation of NPPs (PWRs and PHWRs) increases by 40%.Table 10
Overall scenario cost (unit: M$ based on 2016 USD).
Case I
SC-1
SC-2
Number of PWRs
32
32
Number of PHWRs
4
4
PWR overnight cost
171,955
171,955
PHWR overnight cost
3,329
3,329
PWR O&M cost
6,878
9,604∗
PWR D&D cost
13,756
19,208∗
PHWR O&M cost
133
218∗
PHWR D&D cost
266
435∗
PWR SNF disposal
39,046
54,215
PHWR SNF disposal
5,799
9,497
PWR fuel cost∗∗
86,435
120,012
PHWR fuel cost∗∗
14,648
23,990
Total PWR cost
318,071
374,995
Total PHWR cost
24,175
37,470
Overall scenario cost
342,246
412,465
PWR electricity generation (TWh)
12,380
17,183
PHWR electricity generation (TWh)
672
1,099
Overall electricity generation (TWh)
13,052
18,282
Case II
SC-3
SC-4
Minimum number of SFRs needed
14
24
Operating lifetime of SFR (y)
60
60
SFR overnight cost
51,304
87,949
SFR O&M cost
2,052
3,518
SFR D&D cost
4,104
7,036
SFR fuel cost∗∗
24,402
77,920
Overall scenario cost
82,080
176,796
SFR electricity generation (TWh)
4,014
6,870
Case III
SC-5
SC-6
Minimum number of SFRs needed
20
34
Operating lifetime of SFR (y)
60
60
SFR overnight cost
73,291
124,595
SFR O&M cost
2,932
4,984
SFR D&D cost
5,863
9,968
SFR fuel cost∗∗
34,861
110,387
Overall scenario cost
117,257
250,461
SFR electricity generation (TWh)
5,734
9,732
Case IV
SC-7
SC-8
Minimum number of SFRs needed
15
25
Operating lifetime of SFR (y)
80
80
SFR overnight cost
54,968
91,614
SFR O&M cost
2,932
4,886
SFR D&D cost
5,863
9,772
SFR fuel cost∗∗
34,861
108,222
Overall scenario cost
98,865
214,896
SFR electricity generation (TWh)
5,734
9,541
O&M: operation and management; D&D: decommissioning and decontamination; TWh: terawatt hours.O∗&M and D&D costs in SC-2 are derived from SC-1 for 20 years of a more operational period. PWR∗∗/PHWR/SFR fuel cost represents the total cost of the fuel for the specified type of nuclear reactor.As far as Pyro-SFR scenarios are concerned, overnight cost followed by the fuel cost of SFRs in each scenario contributes most in the overall Pyro-SFR energy systems. From scenarios SC-3 to SC-8, it is noted that each scenario has advantages and disadvantages in terms of cost, electricity generation, and the minimum number of SFRs needed. For example, if it is decided to transmute all TRUs without extending the operational lifetime of PWRs and PHWRs, SC-3 and SC-4 can be adopted for short- and long-term transmutation of TRUs, respectively, considering the cost and electricity generation. The major difference between the two is that SC-3 requires a shorter time and a smaller number of SFRs, eventually thus almost twice economical as compared with SC-4. However, the electricity generation from SC-4 is 41.5% higher as compared with SC-3, which can be regarded as a long-term benefit. In Case III and Case IV, similar analysis can be applicable in terms of scenario cost, minimum number of SFRs needed, and electricity generation in each scenario.Scenarios SC-7 and SC-8 reflect the extended operational lifetime of 20 years for all SFRs in order to transmute all TRUs being generated from SC-2. Upon comparison of Case III scenarios with Case IV scenarios, we found out that the total electricity generation from SC-5 and SC-7 is almost the same but SC-7 is more economical compared with SC-5, as it transmutes the same amount of TRUs with fewer units of SFRs while producing the same amount of electricity. In case of scenarios SC-6 and SC-8, relative electricity benefits between the two differ by 1.97%, as SC-8 generates 98.03% electricity comparable to SC-6, but in terms of cost and transmutation of TRUs from SC-2, SC-6 is 1.2 times more expensive and requires 26.4% more SFRs as compared with SC-8.It is noted that Table10 should not be used for the direct comparison between direct disposal and Pyro-SFR scenarios because each of SC-1 and SC-2 is a complete nuclear energy system while Pyro-SFR scenarios are just part of the whole nuclear energy system. Pyro-SFR scenarios directly depend on PWR and PHWR fuel cycle because TRUs from SC-1 and SC-2 are the only source of fuel for Pyro-SFR fuel cycle scenarios [13, 31].


### 3.4.4. Comparison of Direct Disposal and Closed Nuclear Energy System Cost

In order to compare the economic feasibilities of direct disposal and Pyro-SFR closed fuel cycle, the total scenario costs for Pyro-SFR fuel cycles in Table10 should be further extended by adding the cost of the front part of the fuel cycle (e.g., existing PWRs and PHWRs fuel cycles).For the optimized strategy of closed nuclear energy system, scenarios were selected from Table10 based on the minimum ratio of cost to electricity generation and maximum transmutation of TRUs with the minimum number of SFRs for maximum benefits. For example, scenario SC-2 is chosen as a representative direct disposal scenario because of its higher electricity generation with a smaller increase of cost for continued operation of NPPs (PWRs and PHWRs). Secondly, in order to close the nuclear fuel cycle, scenarios SC-7 and SC-8 were chosen from six Pyro-SFR scenarios because of the minimum number of SFRs to be deployed for the transmutation of larger amounts of TRUs from SC-2 with a lower ratio of cost to electricity generation and higher electricity generation compared with other Pyro-SFR scenarios.The nuclear energy system cost (i.e., the total costs including overnight cost, fuel cost, O&M cost, D&D cost, and SNF disposal cost, if any) for closed fuel cycle is calculated by the combination of scenarios (i.e., CFC-1 by combining SC-2 and SC-7 and CFC-2 by combining SC-2 and SC-8) as shown in Table11. Two of the most affecting factors (i.e., PWR overnight and fuel costs) in SC-2 and two of the most affecting factors in SC-7 and SC-8 (i.e., SFR overnight and fuel costs) consist of the most dominant cost elements in CFC-1 and CFC-2, respectively, as listed in Table 11. It can be noted that CFC-2 is 20.57% cheaper than CFC-1 with only 13.19% less electricity generation because a smaller number of SFRs are needed for CFC-2. From Table 11, we can see that both CFC-1 and CFC-2 can be utilized for different objectives. That is, CFC-2 can be chosen for fast transmutation of TRUs with the minimum number of SFRs. On the other hand, CFC-1 can be selected for extended transmutation of TRUs with a comparatively higher number of SFRs, which generates 13.19% more electricity.Table 11
Estimation of closed nuclear energy system costs (unit: M$ based on 2016 USD).
Parameters
CFC-1
CFC-2
Number of PWRs
31
31
Number of PHWRs
4
4
Minimum number of SFRs needed
25
15
SFR’s CR
0.6
0.46
Operating lifetime (PWR/PHWR/SFR)
60/50/80
60/50/80
SFR overnight cost
91,614
54,968
PWR overnight cost
171,955
171,955
PHWR overnight cost
3,329
3,329
SFR fuel cost
108,222
34,861
PWR fuel cost
120,012
120,012
PHWR fuel cost
23,990
23,990
SFR O&M cost
4,886
2,932
PWR O&M cost
9,604
9,604
PHWR O&M cost
218
218
SFR D&D cost
9,772
5,863
PWR D&D cost
19,208
19,208
PHWR D&D cost
435
435
Closed nuclear energy system cost
563,246
447,376
Electricity generation (TWh)
28,841
25,035
CFC: closed fuel cycle.Table 12
Modified set of equations to estimate the cost of nuclear fuel cycle based on equilibrium model.
Category
Equations
Individual process cost
Cost for conversion ($/kgU) (C(CON))
C
(
C
O
N
)
=
U
C
(
C
O
N
)
⋅
A
(
C
O
N
)
(i)
Cost for enrichment ($/SWU) (C(ENR))
C
(
E
N
R
)
=
U
C
(
S
W
U
)
⋅
A
(
N
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(ii)
Cost for PWR fuel fabrication ($/kgHM) (C(PWRFAB))
C
(
P
W
R
F
A
B
)
=
U
C
(
P
W
R
F
A
B
)
⋅
A
(
F
A
B
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(iii)
Cost for PHWR fuel fabrication ($/kgHM) (C(PHWRFAB))
C
(
P
H
W
R
F
A
B
)
=
U
C
(
P
H
W
R
F
A
B
)
⋅
A
(
F
A
B
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(iv)
Cost for pyroprocessing ($/kgHM) (C(PYRO))
C
(
P
Y
R
O
)
=
U
C
(
P
Y
R
O
)
⋅
A
(
R
E
C
)
+
U
D
(
L
I
-
L
L
)
⋅
A
D
(
L
I
-
L
L
)
+
U
D
(
H
L
W
)
⋅
A
D
(
H
L
W
)
(v)
Cost for SFR fuel fabrication ($/kgHM) (C(SFRFAB))
C
(
S
F
R
F
A
B
)
=
U
C
(
S
F
R
F
A
B
)
⋅
A
(
F
A
B
)
+
C
D
(
L
I
-
L
L
)
⋅
A
D
(
L
I
-
L
L
)
(vi)
Cost for storage and transport ($/kgHM) (C(STR))
C
(
S
T
R
)
=
U
C
(
S
)
⋅
A
(
S
)
+
U
C
(
T
R
)
⋅
A
(
T
R
)
(vii)
Total process cost
Total cost for PWR process ($/kgHM) (C(PWR)P)
C
(
P
W
R
)
P
=
C
(
C
O
N
)
+
C
(
E
N
R
)
+
C
(
P
W
R
F
A
B
)
+
C
(
S
T
R
)
+
C
D
(
S
N
F
)
∗
(viii)
Total cost for PHWR process ($/kgHM) (C(PHWR)P)
C
(
P
H
W
R
)
P
=
C
(
C
O
N
)
+
C
(
P
H
W
R
F
A
B
)
+
C
(
S
T
R
)
+
C
D
(
S
N
F
)
∗
(ix)
Total cost for Pyro-SFR process ($/kgHM) (CPyro-SFRP)
C
P
y
r
o
-
S
F
R
P
=
C
(
P
Y
R
O
)
+
C
(
S
F
R
F
A
B
)
+
C
(
S
T
R
)
(x)
Fuel cycle cost
PWR fuel cycle cost ($/kWh), (CF(PWR))
C
F
(
P
W
R
)
=
C
(
P
W
R
)
P
0.32
M
W
e
/
M
W
t
⋅
45
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xi)
PHWR fuel cycle cost ($/kWh) (CF(PHWR))
C
F
(
P
H
W
R
)
=
C
(
P
H
W
R
)
P
0.32
M
W
e
/
M
W
t
⋅
7.5
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xii)
Pyro-SFR fuel cycle cost ($/kWh), CR = 0.46 (CFPYRO-SFR,CR=0.46)
C
F
P
Y
R
O
-
S
F
R
,
C
R
=
0.46
=
C
P
y
r
o
-
S
F
R
P
0.394
M
W
e
/
M
W
t
⋅
217
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xiii)
Pyro-SFR fuel cycle cost ($/kWh), CR = 0.6 (CFPYRO-SFR,CR=0.6)
C
F
P
Y
R
O
-
S
F
R
,
C
R
=
0.6
=
C
P
y
r
o
-
S
F
R
P
0.394
M
W
e
/
M
W
t
⋅
116.3
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xiv)
C
D
(
S
N
F
)
∗: cost of disposing of spent nuclear fuel from NPPs (PWRs and PHWRs) =AD(SNF)⋅UD(SNF); UC(CON): unit cost of conversion; UC(SWU): unit cost of enrichment; UC(PWRFAB): unit cost of PWR fuel fabrication; UC(PHWRFAB): unit cost of PHWR fuel fabrication; UC(PYRO): unit cost of pyroprocessing; UC(SFRFAB): unit cost for SFR fuel fabrication; UC(S): unit cost of storage; UCTR: unit cost of transportation; UD(LI-SL): unit cost of disposing of low intermediate-short-lived waste; UD(LI-LL): unit cost of disposing of low intermediate-long-lived waste; UD(HLW): unit cost of disposing of high-level waste; UD(SNF): unit cost of disposing of spent nuclear fuel; A(CON): amount of uranium to be converted; A(N): amount for enrichment; A(FAB): amount of fuel to be fabricated; A(REC): amount of fuel to be recycled; A(S): amount of fuel to be stored; A(TR): amount of fuel to be transported; AD(LI-SL): amount of disposing of low intermediate-short-lived waste; AD(LI-LL): amount of disposing of low intermediate-long-lived waste; AD(HLW): amount of disposing of high-level waste; AD(SNF): amount of disposing of spent nuclear fuel; C(PWR)P: total cost of PWR fuel cycle; C(PHWR)P: total cost of PHWR fuel cycle; C(Pyro-SFR)P: total cost of Pyro-SFR fuel cycle; CF(PWR): fuel cycle cost of PWR fuel cycle; CF(PHWR): fuel cycle cost of PHWR fuel cycle; CF(Pyro-SFR)CR=0.46: fuel cycle cost of Pyro-SFRCR=0.46 fuel cycle; CF(Pyro-SFR)CR=0.6: fuel cycle cost of Pyro-SFRCR=0.6 fuel cycle.Figure7 shows the statistics from the Monte Carlo simulation with the assumption that each parameter of direct disposal and closed nuclear energy system has a triangular distribution. A series of Monte Carlo simulations were carried out using 50,000 samples, and the total generation costs for SC-1, SC-2, CFC-1, and CFC-2 are calculated to be 24.497 ± 2.995 (1σ), 21.382 ± 2.318, 19.220 ± 1.817, and 17.620 ± 1.785 $/kWh, respectively. Scenarios SC-1 and SC-2, which are a combination of PWR and PHWR nuclear energy systems, are being considered as a single integrated direct disposal nuclear energy system; hence, the cost incurred at any point in SC-1 and SC-2 should be normalized with the electricity produced throughout SC-1 and SC-2. Similarly, fuel cycle with recycling of TRUs is considered as a single integrated technology; therefore, the cost incurred at any point in the CFC-1 and CFC-2 is normalized across the electricity produced throughout the whole closed fuel cycle [35].Figure 7
Probabilistic estimation of the total generation cost for direct disposal and closed nuclear energy systems using 50,000 samples.


### 3.4.5. Break-Even SFR Overnight Cost

In order to determine a specific condition under which the Pyro-SFR closed nuclear energy system shows positive economic feasibility over direct disposal option, a break-even point of SFR overnight cost is estimated. As shown in Figure8, the break-even SFR overnight cost per reactor for CFC-1 and CFC-2 is calculated to be M$ 2,570 and M$ 3,450, respectively. It can be said that the closed nuclear energy system CFC-1 or CFC-2 is more economically feasible compared to direct disposal scenario SC-2 if SFR overnight cost falls below the break-even point as calculated in the figure.Figure 8
Relation between the break-even points of unit SFR overnight cost with CFC-1, CFC-2, and SC-2.


### 3.4.6. Sensitivity Analysis for Closed Fuel Cycles

Sensitivity analysis has been carried out to analyze the cost elements in closed fuel cycle that may affect the nuclear energy system cost by using Crystal Ball software. Crystal Ball computes the sensitivity by computing rank correlation coefficients. Correlation coefficients measure the strength of the linear relationship among the parameters in CFC-1 and CFC-2. A parameter having a higher correlation coefficient value affects more the total cost of closed nuclear energy system.Figure9 shows that the five most affecting factors in CFC-1 and CFC-2 are the PWR overnight cost, SFR overnight cost, SFR fuel cost, PWR fuel cost, and PHWR fuel cost. As mentioned, it is noted that, even though sensitivity for direct disposal energy system is not conducted, the relative sensitivity of cost elements in SC-1 and SC-2 can be calculated by taking into account the cost parameters related to PWR and PHWRs only from Figure 9.Figure 9
Sensitivity of cost elements in closed fuel cycle nuclear energy systems: (a) CFC-1 and (b) CFC-2.
(a)
(b)


## 3.4.1. Derivation of Process Costs Based upon Unit Costs from Existing Studies

In order to perform front- and back-end fuel cycle cost calculations, a variety of economic studies on nuclear fuel cycles were firstly reviewed and analyzed. It is intended in this study to consider the variabilities and uncertainties of unit cost data as much as possible by expanding the references of unit cost data and using a statistical manipulation. As a result, various domestic and overseas unit cost data available from reliable information resources such as official reports of competent international organizations and selected scientific papers published in international journals were collected as shown in Table8 [14–21, 35–37, 40–44]. All the unit cost data were normalized to the 2016 US dollar values.Table 8
Probability distribution function of nuclear fuel cycle process costs and reactor cost (based on 2016 USD).
Category
Probability distribution
Min
Max
Mean
Unit
References
Uranium∗
Triangular [37]
58
409
219
$/kgU
[14–18, 21, 35–37, 40–44]
Conversion
Uniform [12]
6
33
14
$/kgU
[14–18, 21, 35–37, 40–44]
Enrichment
Uniform [12]
262
411
481
$/SWU
[14–18, 21, 35–37, 40–44]
PWR fuel fabrication
Triangular [37]
281
422
346
$/kgHM
[14–18, 21, 35–37, 40–44]
PHWR fuel fabrication
Triangular [37]
60
186
152
$/kgHM
[17–21, 35, 36, 43]
UO2-pyroprocess
Triangular [37]
882
4,819
3,064
$/kgHM
[14–16, 18–20, 35, 36]
SFR-pyroprocess
Triangular [37]
1,392
5,692
3,786
$/kgHM
[14–16, 18–20, 35, 36]
SFR fuel fabrication
Triangular [37]
2,297
8,680
4,939
$/kgHM
[14–16, 18–20, 35–37, 40, 42]
PWR IS&T
Triangular [37]
133
925
480
$/kgHM
[14–21, 35–37, 40–43]
PHWR IS&T
Triangular [37]
64
701
393
$/kgHM
[17–21]
Pyroprocess HLW (storage)∗
Triangular [37]
124,561
231,612
199,692
$/m3
[15, 16, 19, 20]
LILW-SL disposal∗
Triangular [37]
3,465
4,170
3,818
$/m3
[15, 16, 37, 40]
LILW-LL disposal∗
Triangular [37]
9,240
11,121
9,867
$/m3
[15, 16, 37, 40]
PWR final disposal∗
Triangular [37]
521
2,245
1,107
$/kgHM
[14, 17–21, 37, 40–43]
PHWR final disposal∗
Triangular [37]
106
699
519
$/kgHM
[17–21]
Pyroprocess disposal∗
Triangular [37]
17,361
493,893
296,539
$/kgHM
[14, 15, 18–20, 37, 40, 41, 43]
PWR overnight∗
Triangular [37]
1,919
7,018
4,746
$/kWe
[17, 18, 37, 43]
PHWR overnight∗
Triangular [37]
1,903
3,268
2,587
$/kWe
[37]
SFR overnight∗
Triangular [37]
2,331
9,199
6,115
$/kWe
[17, 18, 40, 43]
IS&T: interim storage and transportation; HLW: high-level waste; LILW-SL: low intermediate level waste-short-lived; LILW-LL: low intermediate level waste-long-lived; Min: minimum; Max: maximum; kgU: kilogram uranium; SWU: separative work unit; KgHM: kilogram heavy metal; m3: cubic meter; USD: US dollar. Values∗ are adopted from different sources, normalized to 2016 USD, statistically analyzed, and presented in this table.In this study, first unit cost data is collected from different studies and statistically analyzed, and then individual process costs (as shown in Table8) were calculated by using the result of analysis as an input to (i) to (vii) from Table 12. The individual process costs were derived again by probabilistic calculation using a commercially available risk analysis software program called Crystal Ball™ utilizing Monte Carlo simulation, which randomly selects values for each input to the model from a distribution specified by the user. The calculation was done by use of (i) to (vii) from Table 12 after defining the parameters of probability distribution for the individual process costs of different nuclear fuel cycles. The other costs except for the individual process costs in Table 8 were derived from statistical analysis of reference unit costs. In accordance with the above methodology, the statistics of costs were calculated as shown in Table 9.Table 9
Descriptive statistics of process cost and reactor cost using 50,000 random samples with Monte Carlo method.
Category
Minimum
Maximum
Mean
Median
SD
CV
Uranium
58.16
407.27
228.89
226.88
71.46
0.31
Conversion
6.20
33.59
19.92
19.97
7.91
0.40
Enrichment
406.21
576.50
487.52
486.34
31.08
0.06
PWR fuel fabrication
284.63
425.83
352.40
351.10
29.04
0.08
PHWR fuel fabrication
63.77
188.97
134.76
137.84
26.48
0.20
UO2-pyroprocess
990.05
5,147.95
3,063.97
3,062.27
809.89
0.26
SFR-pyroprocess
1,514.36
5,963.69
3,765.25
3,774.47
879.01
0.23
SFR fuel fabrication
2,322.11
8,682.88
5,311.27
5,225.73
1,315.30
0.25
PWR IS&T
135.35
923.51
513.05
505.19
161.88
0.32
PHWR IS&T
65.51
699.21
385.24
386.78
130.25
0.34
Pyroprocess HLW (storage)
124,855.22
231,538.87
185,416.02
188,057.06
22,407.71
0.12
LILW-SL disposal
3,467.53
4,166.87
3,817.85
3,817.21
144.40
0.04
LILW-LL disposal
9,246.08
11,119.19
10,074.75
10,033.59
391.76
0.04
PWR final disposal
523.49
2,244.14
1,292.74
1,254.76
359.15
0.28
PHWR final disposal
296.62
698.04
503.64
507.00
83.10
0.16
Pyroprocess disposal
17,870.38
492,381.02
269,486.28
274,929.70
97,445.86
0.36
PWR overnight
1,907.61
7,027.80
4,758.43
4,869.87
1,067.17
0.22
PHWR overnight
105.46
1,896.52
1,197.88
1,258.74
393.91
0.33
SFR overnight
2,321.49
9,196.44
6,107.57
6,254.42
1,438.34
0.24
SD: standard deviation; CV: coefficient of variability.All∗ units are the same as in Table 8 for each item.Precision of the cost values can be analyzed by using the data of coefficient of variability (CV) given in Table9, which compares the variability of cost values relative to the mean or in other words precision of cost values. It is reportedly known that a parameter having a higher value of CV (i.e., dispersion around the mean is higher) is considered to be less precise. The values derived from Crystal Ball simulation can be said to be acceptable, since all values of CV in Table 9 range from 0 to 1 which are typically known to be precise enough [45].Three types of probability distributions, uniform, triangular, and normal distributions, which are typically used for cases where limited amount of sample data is available, as shown in Table8, were used for each cost element in order to quantify the uncertainties in estimation of the costs. The probability distribution of each cost in Table 8 was adopted from studies on economic analysis of nuclear fuel cycle [12, 37].


## 3.4.2. Calculation of Fuel Cycle Costs

Figure6 shows the results of probabilistic calculation of the fuel cycle costs (FCCs) for selected fuel cycle options. With the assumption of probability distribution for each process cost element as stated in Table 8, a series of Monte Carlo simulations using Crystal Ball software were carried out for 50,000 samples to address the inherent uncertainties of the estimated cost. As a result of the simulation, the mean values of FCCs for PWR (direct disposal), PHWR (direct disposal), Pyro-SFR-1 (CR = 0.46), and Pyro-SFR-2 (CR = 0.6) were calculated basically by using (viii) to (xiv) from Table 12 to be 8.174 mills/kWh, 22.114 mills/kWh, 6.065 mills/kWh, and 11.310 mills/kWh, respectively.Figure 6
Probabilistic distribution of fuel cycle cost (FCC).As shown in the statistics of Figure6, the FCC for Pyro-SFR-1 (CR = 0.46) is found to be the most economical fuel cycle option followed by PWR (direct disposal), Pyro-SFR-2 (CR = 0.6), and PHWR (direct disposal). Difference between the FCCs of Pyro-SFR-1 and Pyro-SFR-2 mainly comes from the difference of the values of CR and burnups of SFRs between the two fuel cycles as shown in Table 3. As higher burnup generates more energy per unit mass of fuel; the mass of fuel required for SFR-2 is more than (almost double) that for SFR-1. Accordingly, the FCC in $/kWh for Pyro-SFR-1 turns out to be almost half that for Pyro-SFR-2 due to lower CR and higher burnup [13, 35, 46]. As can be seen from Figure 6, the FCC distribution of PHWR is wider than other fuel cycles and the distribution of Pyro-SFR-1 is narrower than others. It is noted that the peakedness and flatness of a distribution for PWR and Pyro-SFR-1 fuel cycles which resulted in Figure 6 are comparable with previous studies reported [14].


## 3.4.3. Calculation of Scenario Cost

The next step in economic analysis is to estimate the scenario-based cost. As discussed in Tables2 and 7, four cases each consisting of two scenarios are analyzed and presented in Table 10, where the overall scenario cost including overnight cost, fuel cost, operation and management (O&M) cost, and decommissioning and decontamination (D&D) cost for each scenario was calculated by considering the mean value from Table 9. Table 10 shows the breakdown of all the cost elements for two direct disposal and six Pyro-SFR based fuel cycle scenarios. It is noted that the O&M cost and D&D cost are assumed to be calculated as 4% and 8% of overnight cost of reactors in each scenario in accordance with OECD/NEA studies [37]. In case of scenarios SC-1 and SC-2, the most affecting cost elements are PWR overnight cost followed by PWR fuel, PWR SNF disposal, PWR D&D, PHWR fuel cost, and others. The potential of continued operation of NPPs (PWRs and PHWRs) in scenario SC-2 up to an additional twenty years increases the total cost by 20.51%. However, the benefit of additional electricity generation to be obtained from continued operation of NPPs (PWRs and PHWRs) increases by 40%.Table 10
Overall scenario cost (unit: M$ based on 2016 USD).
Case I
SC-1
SC-2
Number of PWRs
32
32
Number of PHWRs
4
4
PWR overnight cost
171,955
171,955
PHWR overnight cost
3,329
3,329
PWR O&M cost
6,878
9,604∗
PWR D&D cost
13,756
19,208∗
PHWR O&M cost
133
218∗
PHWR D&D cost
266
435∗
PWR SNF disposal
39,046
54,215
PHWR SNF disposal
5,799
9,497
PWR fuel cost∗∗
86,435
120,012
PHWR fuel cost∗∗
14,648
23,990
Total PWR cost
318,071
374,995
Total PHWR cost
24,175
37,470
Overall scenario cost
342,246
412,465
PWR electricity generation (TWh)
12,380
17,183
PHWR electricity generation (TWh)
672
1,099
Overall electricity generation (TWh)
13,052
18,282
Case II
SC-3
SC-4
Minimum number of SFRs needed
14
24
Operating lifetime of SFR (y)
60
60
SFR overnight cost
51,304
87,949
SFR O&M cost
2,052
3,518
SFR D&D cost
4,104
7,036
SFR fuel cost∗∗
24,402
77,920
Overall scenario cost
82,080
176,796
SFR electricity generation (TWh)
4,014
6,870
Case III
SC-5
SC-6
Minimum number of SFRs needed
20
34
Operating lifetime of SFR (y)
60
60
SFR overnight cost
73,291
124,595
SFR O&M cost
2,932
4,984
SFR D&D cost
5,863
9,968
SFR fuel cost∗∗
34,861
110,387
Overall scenario cost
117,257
250,461
SFR electricity generation (TWh)
5,734
9,732
Case IV
SC-7
SC-8
Minimum number of SFRs needed
15
25
Operating lifetime of SFR (y)
80
80
SFR overnight cost
54,968
91,614
SFR O&M cost
2,932
4,886
SFR D&D cost
5,863
9,772
SFR fuel cost∗∗
34,861
108,222
Overall scenario cost
98,865
214,896
SFR electricity generation (TWh)
5,734
9,541
O&M: operation and management; D&D: decommissioning and decontamination; TWh: terawatt hours.O∗&M and D&D costs in SC-2 are derived from SC-1 for 20 years of a more operational period. PWR∗∗/PHWR/SFR fuel cost represents the total cost of the fuel for the specified type of nuclear reactor.As far as Pyro-SFR scenarios are concerned, overnight cost followed by the fuel cost of SFRs in each scenario contributes most in the overall Pyro-SFR energy systems. From scenarios SC-3 to SC-8, it is noted that each scenario has advantages and disadvantages in terms of cost, electricity generation, and the minimum number of SFRs needed. For example, if it is decided to transmute all TRUs without extending the operational lifetime of PWRs and PHWRs, SC-3 and SC-4 can be adopted for short- and long-term transmutation of TRUs, respectively, considering the cost and electricity generation. The major difference between the two is that SC-3 requires a shorter time and a smaller number of SFRs, eventually thus almost twice economical as compared with SC-4. However, the electricity generation from SC-4 is 41.5% higher as compared with SC-3, which can be regarded as a long-term benefit. In Case III and Case IV, similar analysis can be applicable in terms of scenario cost, minimum number of SFRs needed, and electricity generation in each scenario.Scenarios SC-7 and SC-8 reflect the extended operational lifetime of 20 years for all SFRs in order to transmute all TRUs being generated from SC-2. Upon comparison of Case III scenarios with Case IV scenarios, we found out that the total electricity generation from SC-5 and SC-7 is almost the same but SC-7 is more economical compared with SC-5, as it transmutes the same amount of TRUs with fewer units of SFRs while producing the same amount of electricity. In case of scenarios SC-6 and SC-8, relative electricity benefits between the two differ by 1.97%, as SC-8 generates 98.03% electricity comparable to SC-6, but in terms of cost and transmutation of TRUs from SC-2, SC-6 is 1.2 times more expensive and requires 26.4% more SFRs as compared with SC-8.It is noted that Table10 should not be used for the direct comparison between direct disposal and Pyro-SFR scenarios because each of SC-1 and SC-2 is a complete nuclear energy system while Pyro-SFR scenarios are just part of the whole nuclear energy system. Pyro-SFR scenarios directly depend on PWR and PHWR fuel cycle because TRUs from SC-1 and SC-2 are the only source of fuel for Pyro-SFR fuel cycle scenarios [13, 31].


## 3.4.4. Comparison of Direct Disposal and Closed Nuclear Energy System Cost

In order to compare the economic feasibilities of direct disposal and Pyro-SFR closed fuel cycle, the total scenario costs for Pyro-SFR fuel cycles in Table10 should be further extended by adding the cost of the front part of the fuel cycle (e.g., existing PWRs and PHWRs fuel cycles).For the optimized strategy of closed nuclear energy system, scenarios were selected from Table10 based on the minimum ratio of cost to electricity generation and maximum transmutation of TRUs with the minimum number of SFRs for maximum benefits. For example, scenario SC-2 is chosen as a representative direct disposal scenario because of its higher electricity generation with a smaller increase of cost for continued operation of NPPs (PWRs and PHWRs). Secondly, in order to close the nuclear fuel cycle, scenarios SC-7 and SC-8 were chosen from six Pyro-SFR scenarios because of the minimum number of SFRs to be deployed for the transmutation of larger amounts of TRUs from SC-2 with a lower ratio of cost to electricity generation and higher electricity generation compared with other Pyro-SFR scenarios.The nuclear energy system cost (i.e., the total costs including overnight cost, fuel cost, O&M cost, D&D cost, and SNF disposal cost, if any) for closed fuel cycle is calculated by the combination of scenarios (i.e., CFC-1 by combining SC-2 and SC-7 and CFC-2 by combining SC-2 and SC-8) as shown in Table11. Two of the most affecting factors (i.e., PWR overnight and fuel costs) in SC-2 and two of the most affecting factors in SC-7 and SC-8 (i.e., SFR overnight and fuel costs) consist of the most dominant cost elements in CFC-1 and CFC-2, respectively, as listed in Table 11. It can be noted that CFC-2 is 20.57% cheaper than CFC-1 with only 13.19% less electricity generation because a smaller number of SFRs are needed for CFC-2. From Table 11, we can see that both CFC-1 and CFC-2 can be utilized for different objectives. That is, CFC-2 can be chosen for fast transmutation of TRUs with the minimum number of SFRs. On the other hand, CFC-1 can be selected for extended transmutation of TRUs with a comparatively higher number of SFRs, which generates 13.19% more electricity.Table 11
Estimation of closed nuclear energy system costs (unit: M$ based on 2016 USD).
Parameters
CFC-1
CFC-2
Number of PWRs
31
31
Number of PHWRs
4
4
Minimum number of SFRs needed
25
15
SFR’s CR
0.6
0.46
Operating lifetime (PWR/PHWR/SFR)
60/50/80
60/50/80
SFR overnight cost
91,614
54,968
PWR overnight cost
171,955
171,955
PHWR overnight cost
3,329
3,329
SFR fuel cost
108,222
34,861
PWR fuel cost
120,012
120,012
PHWR fuel cost
23,990
23,990
SFR O&M cost
4,886
2,932
PWR O&M cost
9,604
9,604
PHWR O&M cost
218
218
SFR D&D cost
9,772
5,863
PWR D&D cost
19,208
19,208
PHWR D&D cost
435
435
Closed nuclear energy system cost
563,246
447,376
Electricity generation (TWh)
28,841
25,035
CFC: closed fuel cycle.Table 12
Modified set of equations to estimate the cost of nuclear fuel cycle based on equilibrium model.
Category
Equations
Individual process cost
Cost for conversion ($/kgU) (C(CON))
C
(
C
O
N
)
=
U
C
(
C
O
N
)
⋅
A
(
C
O
N
)
(i)
Cost for enrichment ($/SWU) (C(ENR))
C
(
E
N
R
)
=
U
C
(
S
W
U
)
⋅
A
(
N
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(ii)
Cost for PWR fuel fabrication ($/kgHM) (C(PWRFAB))
C
(
P
W
R
F
A
B
)
=
U
C
(
P
W
R
F
A
B
)
⋅
A
(
F
A
B
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(iii)
Cost for PHWR fuel fabrication ($/kgHM) (C(PHWRFAB))
C
(
P
H
W
R
F
A
B
)
=
U
C
(
P
H
W
R
F
A
B
)
⋅
A
(
F
A
B
)
+
U
D
(
L
I
-
S
L
)
⋅
A
D
(
L
I
-
S
L
)
(iv)
Cost for pyroprocessing ($/kgHM) (C(PYRO))
C
(
P
Y
R
O
)
=
U
C
(
P
Y
R
O
)
⋅
A
(
R
E
C
)
+
U
D
(
L
I
-
L
L
)
⋅
A
D
(
L
I
-
L
L
)
+
U
D
(
H
L
W
)
⋅
A
D
(
H
L
W
)
(v)
Cost for SFR fuel fabrication ($/kgHM) (C(SFRFAB))
C
(
S
F
R
F
A
B
)
=
U
C
(
S
F
R
F
A
B
)
⋅
A
(
F
A
B
)
+
C
D
(
L
I
-
L
L
)
⋅
A
D
(
L
I
-
L
L
)
(vi)
Cost for storage and transport ($/kgHM) (C(STR))
C
(
S
T
R
)
=
U
C
(
S
)
⋅
A
(
S
)
+
U
C
(
T
R
)
⋅
A
(
T
R
)
(vii)
Total process cost
Total cost for PWR process ($/kgHM) (C(PWR)P)
C
(
P
W
R
)
P
=
C
(
C
O
N
)
+
C
(
E
N
R
)
+
C
(
P
W
R
F
A
B
)
+
C
(
S
T
R
)
+
C
D
(
S
N
F
)
∗
(viii)
Total cost for PHWR process ($/kgHM) (C(PHWR)P)
C
(
P
H
W
R
)
P
=
C
(
C
O
N
)
+
C
(
P
H
W
R
F
A
B
)
+
C
(
S
T
R
)
+
C
D
(
S
N
F
)
∗
(ix)
Total cost for Pyro-SFR process ($/kgHM) (CPyro-SFRP)
C
P
y
r
o
-
S
F
R
P
=
C
(
P
Y
R
O
)
+
C
(
S
F
R
F
A
B
)
+
C
(
S
T
R
)
(x)
Fuel cycle cost
PWR fuel cycle cost ($/kWh), (CF(PWR))
C
F
(
P
W
R
)
=
C
(
P
W
R
)
P
0.32
M
W
e
/
M
W
t
⋅
45
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xi)
PHWR fuel cycle cost ($/kWh) (CF(PHWR))
C
F
(
P
H
W
R
)
=
C
(
P
H
W
R
)
P
0.32
M
W
e
/
M
W
t
⋅
7.5
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xii)
Pyro-SFR fuel cycle cost ($/kWh), CR = 0.46 (CFPYRO-SFR,CR=0.46)
C
F
P
Y
R
O
-
S
F
R
,
C
R
=
0.46
=
C
P
y
r
o
-
S
F
R
P
0.394
M
W
e
/
M
W
t
⋅
217
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xiii)
Pyro-SFR fuel cycle cost ($/kWh), CR = 0.6 (CFPYRO-SFR,CR=0.6)
C
F
P
Y
R
O
-
S
F
R
,
C
R
=
0.6
=
C
P
y
r
o
-
S
F
R
P
0.394
M
W
e
/
M
W
t
⋅
116.3
M
W
d
/
k
g
H
M
⋅
24,000
k
W
h
/
M
W
d
(xiv)
C
D
(
S
N
F
)
∗: cost of disposing of spent nuclear fuel from NPPs (PWRs and PHWRs) =AD(SNF)⋅UD(SNF); UC(CON): unit cost of conversion; UC(SWU): unit cost of enrichment; UC(PWRFAB): unit cost of PWR fuel fabrication; UC(PHWRFAB): unit cost of PHWR fuel fabrication; UC(PYRO): unit cost of pyroprocessing; UC(SFRFAB): unit cost for SFR fuel fabrication; UC(S): unit cost of storage; UCTR: unit cost of transportation; UD(LI-SL): unit cost of disposing of low intermediate-short-lived waste; UD(LI-LL): unit cost of disposing of low intermediate-long-lived waste; UD(HLW): unit cost of disposing of high-level waste; UD(SNF): unit cost of disposing of spent nuclear fuel; A(CON): amount of uranium to be converted; A(N): amount for enrichment; A(FAB): amount of fuel to be fabricated; A(REC): amount of fuel to be recycled; A(S): amount of fuel to be stored; A(TR): amount of fuel to be transported; AD(LI-SL): amount of disposing of low intermediate-short-lived waste; AD(LI-LL): amount of disposing of low intermediate-long-lived waste; AD(HLW): amount of disposing of high-level waste; AD(SNF): amount of disposing of spent nuclear fuel; C(PWR)P: total cost of PWR fuel cycle; C(PHWR)P: total cost of PHWR fuel cycle; C(Pyro-SFR)P: total cost of Pyro-SFR fuel cycle; CF(PWR): fuel cycle cost of PWR fuel cycle; CF(PHWR): fuel cycle cost of PHWR fuel cycle; CF(Pyro-SFR)CR=0.46: fuel cycle cost of Pyro-SFRCR=0.46 fuel cycle; CF(Pyro-SFR)CR=0.6: fuel cycle cost of Pyro-SFRCR=0.6 fuel cycle.Figure7 shows the statistics from the Monte Carlo simulation with the assumption that each parameter of direct disposal and closed nuclear energy system has a triangular distribution. A series of Monte Carlo simulations were carried out using 50,000 samples, and the total generation costs for SC-1, SC-2, CFC-1, and CFC-2 are calculated to be 24.497 ± 2.995 (1σ), 21.382 ± 2.318, 19.220 ± 1.817, and 17.620 ± 1.785 $/kWh, respectively. Scenarios SC-1 and SC-2, which are a combination of PWR and PHWR nuclear energy systems, are being considered as a single integrated direct disposal nuclear energy system; hence, the cost incurred at any point in SC-1 and SC-2 should be normalized with the electricity produced throughout SC-1 and SC-2. Similarly, fuel cycle with recycling of TRUs is considered as a single integrated technology; therefore, the cost incurred at any point in the CFC-1 and CFC-2 is normalized across the electricity produced throughout the whole closed fuel cycle [35].Figure 7
Probabilistic estimation of the total generation cost for direct disposal and closed nuclear energy systems using 50,000 samples.


## 3.4.5. Break-Even SFR Overnight Cost

In order to determine a specific condition under which the Pyro-SFR closed nuclear energy system shows positive economic feasibility over direct disposal option, a break-even point of SFR overnight cost is estimated. As shown in Figure8, the break-even SFR overnight cost per reactor for CFC-1 and CFC-2 is calculated to be M$ 2,570 and M$ 3,450, respectively. It can be said that the closed nuclear energy system CFC-1 or CFC-2 is more economically feasible compared to direct disposal scenario SC-2 if SFR overnight cost falls below the break-even point as calculated in the figure.Figure 8
Relation between the break-even points of unit SFR overnight cost with CFC-1, CFC-2, and SC-2.


## 3.4.6. Sensitivity Analysis for Closed Fuel Cycles

Sensitivity analysis has been carried out to analyze the cost elements in closed fuel cycle that may affect the nuclear energy system cost by using Crystal Ball software. Crystal Ball computes the sensitivity by computing rank correlation coefficients. Correlation coefficients measure the strength of the linear relationship among the parameters in CFC-1 and CFC-2. A parameter having a higher correlation coefficient value affects more the total cost of closed nuclear energy system.Figure9 shows that the five most affecting factors in CFC-1 and CFC-2 are the PWR overnight cost, SFR overnight cost, SFR fuel cost, PWR fuel cost, and PHWR fuel cost. As mentioned, it is noted that, even though sensitivity for direct disposal energy system is not conducted, the relative sensitivity of cost elements in SC-1 and SC-2 can be calculated by taking into account the cost parameters related to PWR and PHWRs only from Figure 9.Figure 9
Sensitivity of cost elements in closed fuel cycle nuclear energy systems: (a) CFC-1 and (b) CFC-2.
(a)
(b)


## 4. Conclusion

The total inventory of SNF to be produced from all thirty-six units of NPPs that are in operation or will be deployed by 2029 is estimated to be 41,718 MTU, in accordance with the national policy of the Korean government in 2016. It is also found that the continued operation of NPPs may increase the national inventory of SNF by 47% (i.e., up to 61,232 MTHM). In this study, it is reconfirmed that the nominal radiotoxicity index of the long-lived TRUs in the SNF will decrease down to the level of natural uranium at least after 200,000 years of radioactive decay as reportedly known.Based on a series of reasonable assumptions derived from past experience of nuclear power development in Korea and the government’s future plan, the minimum number of SFRs required to transmute all TRUs is calculated to be 14 to 34, and the full transmutation of TRUs is expected to be completed in 2109 to 2153. The key technical elements determining the optimized strategy for SFR deployment are the design features of SFR (e.g., conversion ratio, burnup), the deployment rate of SFRs, and the target year for completion of transmutation of TRUs.A systematic stepwise procedure to conduct the probabilistic economic analysis of nuclear energy system is proposed in this study (see Figure2). From balanced comparison of the whole cost and all benefits from direct disposal and Pyro-SFR recycling options, the total generation costs for direct disposal and Pyro-SFR nuclear energy systems are estimated to be 13.60~33.94 mills/kWh and 11.40~25.91 mills/kWh, respectively. It is concluded that the relative feasibility of each scenario can be assessed based upon the three factors: lower ratio of cost to electricity generation, transmutation of more TRUs with minimum units of SFRs, and higher generation of electricity in order to formulate the optimum closed nuclear energy system.As a result of the sensitivity analysis, the most affecting parameters to the nuclear energy system costs of the closed fuel cycle are as follows in order of contribution: PWR overnight cost, PWR fuel cost, SFR overnight cost, and SFR fuel cost. Since the overnight cost and the fuel cost for PWR are almost invariable in the commercialized nuclear energy system in Korea, however, the overnight cost of the SFR still under development will be the most uncertain cost element to the economics of the closed nuclear energy system. It is also pointed out that the economic feasibility of the closed nuclear energy system is higher than the direct disposal option as long as the SFR overnight cost per reactor can be kept below M$ 2,570 or M$ 3,450 (i.e., the break-even reactor cost) depending upon the design features of the SFR such as conversion ratio.It is expected that the results of this study on the quantitative and economic feasibilities of direct disposal and Pyro-SFR fuel cycle options can be used as a comprehensive reference for the systematic decision-making on the direction of the future nuclear energy system in Korea, which is planned to be made around 2020.



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*Source: 1953256-2017-10-31.xml*