Preliminary Study on Nuclear Fuel Cycle Scenarios of China before 2050

Cao, Bo; Wu, Jun; Yang, Tongrui; Ma, Xubo; Chen, Yixue

doi:10.1016/j.egypro.2013.07.216

Cited by 8 publications

(12 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…i) Uranium fuel consumption M Fuel [t U ] has been estimated based on the thermal power of the reactors, their load factor and burn‐up rate as follows [Eq. ]:

true M_{normalF normalu normale normall} = \frac{N_{T} \times 365 \times C F}{B_{normald}}

…”

Section: Methodsmentioning

confidence: 99%

“…ii) The estimated amount of uranium fuel was then used to calculate the requirement for natural uranium M nat (0.7 % 235 U; [t U ]) for each reactor over the period according to Equation :

true M_{normalN normala normalt} = M_{normalC normalo normaln normalv} \times \frac{1}{r} = M_{normalE normaln} \times \frac{X_{normalE normaln} - X_{normalD normalU}}{X_{normalN normala normalt} - X_{normalD normalU}} \times \frac{1}{r} \Rightarrow M_{normalF normalu normale normall} \times \frac{X_{normalE normaln} - X_{normalD normalU}}{X_{normalN normala normalt} - X_{normalD normalU}} \times \frac{1}{r^{3}}

…”

Section: Methodsmentioning

confidence: 99%

“…where M Conv is the input of UF 6 in the enrichment stage [t U ], r is the uranium recovery rate during natural uranium conversion, production of UO 2 , and fuel fabrication, with r equal to 0.995 for each step . M En is the amount of enriched uranium [t U ], X Nat , X En , and X DU represent the percentage content of 235 U in the natural, enriched, and depleted uranium, respectively, with X Nat =0.7 %, X En =3–4 %, and X DU =0.2–0.3 % …”

Section: Methodsmentioning

confidence: 99%

“…Previous work includes an analysis of pre‐2020 scenarios for natural uranium demand and separative work as well as the amount of spent fuel arising . Similar research has also considered potential scenarios to 2050 . No previous work has attempted to analyze the flows and stocks of nuclear fuel in China, so that at present, it is not clear if and how the country would be able to meet the fast‐growing demand for this resource and what implications that may have globally in a resource‐constrained world.…”

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Nuclear Power in China: An Analysis of the Current and Near‐Future Uranium Flows

Yue

Stamford

et al. 2016

Energy Tech

View full text Add to dashboard Cite

Nuclear power capacity is growing rapidly in China and is expected to reach 58 GW by 2020. However, it is not clear at present if the country can meet this increasing demand for uranium. We present a comprehensive uranium flow analysis in China that covers a ten‐year period from 2003 to 2012 with the aim of identifying near‐future fuel demand to 2020. The findings suggest that from 2003 to 2012, 19 126 t of natural uranium were consumed, which generated 3811 t of spent fuel. Of this, only 33–58 % of natural uranium was sourced domestically, the rest of which was imported. By 2020, the uranium consumption is estimated to reach 14 426 t yr−1, around three quarters of the amount consumed over the whole ten‐year period considered here. Based on the current increase in demand, the domestic natural uranium could run out by 2027 if the country relies solely on its own uranium deposits known currently. Our findings also show that China would need to expand its spent‐fuel reprocessing program, expected to start in 2025, by 3–4 times as the planned capacity is insufficient given the current growth of nuclear power.

show abstract

“…i) Uranium fuel consumption M Fuel [t U ] has been estimated based on the thermal power of the reactors, their load factor and burn‐up rate as follows [Eq. ]:

true M_{normalF normalu normale normall} = \frac{N_{T} \times 365 \times C F}{B_{normald}}

…”

Section: Methodsmentioning

confidence: 99%

“…ii) The estimated amount of uranium fuel was then used to calculate the requirement for natural uranium M nat (0.7 % 235 U; [t U ]) for each reactor over the period according to Equation :

true M_{normalN normala normalt} = M_{normalC normalo normaln normalv} \times \frac{1}{r} = M_{normalE normaln} \times \frac{X_{normalE normaln} - X_{normalD normalU}}{X_{normalN normala normalt} - X_{normalD normalU}} \times \frac{1}{r} \Rightarrow M_{normalF normalu normale normall} \times \frac{X_{normalE normaln} - X_{normalD normalU}}{X_{normalN normala normalt} - X_{normalD normalU}} \times \frac{1}{r^{3}}

…”

Section: Methodsmentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Nuclear Power in China: An Analysis of the Current and Near‐Future Uranium Flows

Yue

Stamford

et al. 2016

Energy Tech

View full text Add to dashboard Cite

show abstract

“…Countries like European countries, USA, Japan, China that have a reprocessing plant will be able to reprocess of their spent fuel [2][3][4]. Indeed, uranium and plutonium are separated from other nuclides, and then assemblied into new nuclear fuel.…”

Section: Introductionmentioning

confidence: 99%

Fuel Burn-Up Distribution and Transuranic Nuclide Contents Produced at the First Cycle Operation of Ap1000

Susilo

Pane²

2016

Tri Dasa Mega

View full text Add to dashboard Cite

FUEL BURN-UP DISTRIBUTION AND TRANSURANIC NUCLIDE CONTENTS PRODUCED ATTHE FIRST CYCLE OPERATION OF AP1000. AP1000 reactor core was designed with nominal power of 1154 MWe (3415 MWth), operated within life time of 60 years and cycle length of 18 months. For the first cycle, the AP1000 core uses three kinds of UO 2 enrichment, they are 2.35 w/o, 3.40 w/o and 4.45 w/o. Absorber materials such as ZrB 2 , Pyrex and Boron solution are used to compensate the excess reactivity at the beginning of cycle. In the core, U-235 fuels are burned by fission reaction and produce energy, fission products and new neutron. Because of the U-238 neutron absoption reaction, the high level radioactive waste of heavy nuclide transuranic such as Pu, Am, Cm and Np are also generated. They have a very long half life. The purpose of this study is to evaluate the result of fuel burn-up distribution and heavy nuclide transuranic contents produced by AP1000 at the end of first cycle operation (EOFC). Calculation of ¼ part of the AP1000 core in the 2 dimensional model has been done using SRAC2006 code with the module of COREBN/HIST. The input data called the table of macroscopic crossection, is calculated using module of PIJ. The result shows that the maximum fuel assembly (FA) burn-up is 27.04 GWD/MTU, that is still lower than allowed maximum burn-up of 62 GWD/MTU. Fuel loading position at the center/middle of the core will produce bigger burn-up and transuranic nuclide than one at the edges the of the core. The use of IFBA fuel just give a small effect to lessen the fuel burn-up and transuranic nuclide production.

show abstract

Performance modeling and analysis of spent nuclear fuel recycling

Gao

Choi

Zhou

et al. 2015

Int. J. Energy Res.

View full text Add to dashboard Cite

SUMMARYThe rapid expansion of nuclear energy in China has intensified concerns regarding spent fuel management. However, the consequences of failure or delay in developing approaches to managing spent fuel in China have not yet been explicitly analyzed. Thus, a dynamic analysis of transitions in nuclear fuel cycles in China to 2050 was conducted. This multidisciplinary study compares the environmental, security, and economic consequences of choices among ongoing technology development options for spent fuel management. Four transition scenarios were identified: the direct disposal of PWR (Pressurized Water Reactor) spent fuel, the recycling of PWR spent fuel through PWR-MOX (Mixed Oxides), the PWR-MOX followed by fast reactors, and the recycling of PWR spent fuel using fast reactors. Direct disposal would have the lowest cost of electricity generation under the current market conditions, while the reprocessing and recycling of PWR spent fuel would benefit the Chinese nuclear power program by reducing the generation of high level waste (67-82%), saving natural U resources (9-17%), and reducing Pu management risk (24-58%). Moreover, a fast reactor system would provide better performance than one-time recycling through PWR-MOX. The latter also poses high risks in managing the build-up of separated Pu.

show abstract

Preliminary Study on Nuclear Fuel Cycle Scenarios of China before 2050

Cited by 8 publications

References 0 publications

Nuclear Power in China: An Analysis of the Current and Near‐Future Uranium Flows

Nuclear Power in China: An Analysis of the Current and Near‐Future Uranium Flows

Fuel Burn-Up Distribution and Transuranic Nuclide Contents Produced at the First Cycle Operation of Ap1000

Performance modeling and analysis of spent nuclear fuel recycling

Contact Info

Product

Resources

About