Used fuel characteristics of once-through fuel cycle with pressurized thermal reactor (EG01)

2015 ◽  
Author(s):  
N. Stauff ◽  
F. Heidet ◽  
T. Kim ◽  
T. Taiwo
Keyword(s):  
Fuel Cycle ◽  
Thermal Reactor ◽  
Fuel Characteristics

scholarly journals Minor actinides transmutation in equilibrium cores of next generation FRs

2019 ◽  
Vol 5 (4) ◽  
pp. 353-359
Author(s):  
Alexander V. Egorov ◽  
Yurii S. Khomyakov ◽  
Valerii I. Rachkov ◽  
Elena A. Rodina ◽  
Igor R. Suslov
Keyword(s):  
Isotopic Composition ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Synergetic Effect ◽  
Transient State ◽  
Advanced Technology ◽  
Thermal Reactor ◽  
Spent Fuel ◽  
Operating Period ◽  
Nitride Fuel

The Russian Federation is developing a number of technologies within the «Proryv» project for closing the nuclear fuel cycle utilizing mixed (U-Pu-MA) nitride fuel. Key objectives of the project include improving fast reactor nuclear safety by minimizing reactivity changes during fuel operating period and improving radiological and environmental fuel cycle safety through Pu multi-recycling and МА transmutation. This advanced technology is expected to allow operating the reactor in an equilibrium cycle with a breeding ratio equaling approximately 1 with stable reactivity and fuel isotopic composition. Nevertheless, to reach this state the reactor must still operate in an initial transient state for a lengthy period (over 10 years) of time, which requires implementing special measures concerning reactivity control. The results obtained from calculations show the possibility of achieving a synergetic effect from combining two objectives. Using МА reprocessed from thermal reactor spent fuel in initial fuel loads in FR ensures a minimal reactivity margin during the entire fast reactor fuel operating period, comparable to the levels achieved in equilibrium state with any kind of relevant Pu isotopic composition. This should be combined with using reactivity compensators in the first fuel micro-campaigns. In the paper presented are the results of simulation of the overall life cycle of a 1200 MWe fast reactor, reaching equilibrium fuel composition, and respective changes in spent fuel nuclide and isotopic composition. It is shown that МА from thermal and fast reactors spent fuel can be completely utilized in the new generation FRs without using special actinide burners.

CANDU Position and Prospect in Chinese Nuclear Fuel Cycle

2013 ◽  
Author(s):  
Zhenhua Zhang ◽  
Mingjun Chen ◽  
Peide Zhou ◽  
Qing Li ◽  
Zhiliang Meng ◽  
...  
Keyword(s):  
Nuclear Power ◽  
High Efficiency ◽  
Fuel Cycle ◽  
System Development ◽  
Natural Uranium ◽  
Thermal Reactor ◽  
Closed Fuel Cycle ◽  
Power Company ◽  
Company Limited ◽  
Reprocessed Uranium

To manage climate challenge and optimize energy supply structure, China has decided to develop more nuclear power in a safe and high-efficiency manner. On a nuclear sustainable development perspective, it is necessary to develop a closed fuel cycle (CFC) system and also take great efforts to improve natural uranium (NU) utilization ratio of thermal reactor. CANDU is great certainty to play an important role in this strategy. This paper presents CNNC Third Qinshan Nuclear Power Company Limited (TQNPC) efforts of being develop the engineering technologies of recycling reprocessed uranium (RU) and nuclear use of thorium (Th) resource in CANDU type reactor and finding the CANDU’s position in Chinese CFC system. Also this paper provides a proposal of implementation plan for Chinese CFC system development and also for application of the related CANDU engineering technologies.

scholarly journals Economic Evaluation on the MOX Fuel in the Closed Fuel Cycle

2012 ◽  
Vol 2012 ◽  
pp. 1-9 ◽  
Author(s):  
Youqi Zheng ◽  
Hongchun Wu ◽  
Liangzhi Cao ◽  
Shizhuang Jia
Keyword(s):  
Fuel Cycle ◽  
Thermal Reactor ◽  
Pressurized Water Reactor ◽  
Fuel Cost ◽  
Analysis Model ◽  
Closed Fuel Cycle ◽  
Pressurized Water ◽  
Mox Fuel ◽  
The Cost ◽  
Current Operating

The mixed oxide (MOX) fuel is one of the most important fuels for the advanced reactors in the future. It is flexible to be applied either in the thermal reactor like pressurized water reactor (PWR) or in the fast reactor (FR). This paper compares the two approaches from the view of fuel cost. Two features are involved. (1) The cost of electricity (COE) is investigated based on the simulation of realistic operation of a practical PWR power plant and a typical fast breeder reactor design. (2) A new economic analysis model is established, considering the discount rate and the revenue of the reprocessed plutonium besides the traditional costs in the processes of fuel cycle. The sensitivity of COE to the changing parameters is also analyzed. The results show that, in the closed fuel cycle, the fuel cost of applying MOX fuels in the FBR is about 25% lower than that in the PWR at the current operating and fuel cycle level.

Environmental aspects of the fast reactor fuel cycle

1990 ◽  
Vol 331 (1619) ◽  
pp. 395-408 ◽  
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Thermal Reactor ◽  
Environmental Aspects ◽  
Fuel Cycles ◽  
Global Environmental ◽  
Delay Times ◽  
Fast Reactor Fuel ◽  
Reactor Accidents

The main characteristics that differentiate a developed fast reactor fuel cycle from the thermal reactor fuel cycles operating now are the higher fissile content of the fuel, the greater incentive to reprocess fuel at shorter delay times and the elimination of uranium mining. The local and global environmental impacts of a typical fuel cycle normalized to 1GW e a of output are estimated, including those from the fabrication, transport and reprocessing of fuel and from reactor operations. Radioactive emissions and radiation doses arising from these operations are compared with those from thermal reactor cycles. The risks of accidental discharges from reprocessing plants are discussed, but reactor accidents are not included. The requirements for safeguards are described. Typical inventories of radioactive wastes arising from reprocessing and from decommissioning have been calculated; the management and disposal of these wastes will pose no significant new problems. The overall result is that a transition from thermal to fast reactor fuel cycles should not result in any increase in environmental impact.

scholarly journals Burning high-level TRU waste in fusion fission reactors

2016 ◽  
Vol 44 ◽  
pp. 1660227
Author(s):  
Yaosong Shen
Keyword(s):  
Neutron Spectrum ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Operation Time ◽  
Thermal Reactor ◽  
Fusion Neutron ◽  
Fission Reactor ◽  
Biological Hazard ◽  
High Level ◽  
Data Libraries

Recently, the concept of actinide burning instead of a once-through fuel cycle for disposing spent nuclear fuel seems to get much more attention. A new method of burning high-level transuranic (TRU) waste combined with Thorium–Uranium (Th–U) fuel in the subcritical reactors driven by external fusion neutron sources is proposed in this paper. The thorium-based TRU fuel burns all of the long-lived actinides via a hard neutron spectrum while outputting power. A one-dimensional model of the reactor concept was built by means of the ONESN_BURN code with new data libraries. The numerical results included actinide radioactivity, biological hazard potential, and much higher burnup rate of high-level transuranic waste. The comparison of the fusion–fission reactor with the thermal reactor shows that the harder neutron spectrum is more efficient than the soft. The Th–U cycle produces less TRU, less radiotoxicity and fewer long-lived actinides. The Th–U cycle provides breeding of [Formula: see text]U with a long operation time (>20 years), hence significantly reducing the reactivity swing while improving safety and burnup.

Euratom R&D Programmes on the Back-End of the Fuel Cycle

2005 ◽  
pp. 84-93
Author(s):  
M. Hugon ◽  
V. P. Bhatnagar ◽  
S. Casalta ◽  
M. Raynal ◽  
S. Webster
Keyword(s):  
Fuel Cycle
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