Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle

1995 ◽  
Vol 121 (1) ◽  
pp. 17-31 ◽  
Author(s):  
R. N. Hill ◽  
D. C. Wade ◽  
J. R. Liaw ◽  
E. K. Fujita
Author(s):  
Daogang Lu ◽  
Chao Guo ◽  
Danting Sui

In the GEN IV technology evaluations, the LMFBR (Liquid Metal Fast Breeder Reactor) system which includes SFR (Sodium-cooled Fast Reactor) and LFR (Lead-cooled Fast Reactor) was top-ranked in sustainability due to its closed fuel cycle and it is top-ranked in proliferation resistance and physical protection because it employs a long-life core. It is necessary to conduct the coupled neutronics and thermal-hydraulics simulation when the feedback effects are significant in the safety analysis of Anticipated Transients Without Scram (ATWS) in LMFBR. Thus, a neutronics-thermalhydraulics coupling code for safety analysis of LMFBR was developed and used to analyze whole-plant transient behavior of the Experimental Breeder Reactor II (EBR-II) under Loss of Heat Sink Without Scram (LOHSWS) tests in this paper. The two mixing zone method for cold pool coupled with SAC-CFR was used and the predicted results agree well with measurements which are taken from EBR-II LOHSWS test data.


2007 ◽  
Vol 157 (2) ◽  
pp. 185-199 ◽  
Author(s):  
W. F. G. van Rooijen ◽  
J. L. Kloosterman ◽  
T. H. J. J. van der Hagen ◽  
H. van Dam

2009 ◽  
Vol 2009 ◽  
pp. 1-9 ◽  
Author(s):  
W. F. G. van Rooijen ◽  
J. L. Kloosterman

The Generation IV International Forum has identified the Gas-Cooled Fast Reactor (GCFR) as one of the reactor concepts for future deployment. The GCFR targets sustainability, which is achieved by the use of a closed nuclear fuel cycle where only fission products are discharged to a repository; all Heavy Metal isotopes are to be recycled in the reactor. In this paper, an overview is presented of recent results obtained in the study of the closed fuel cycle and the influence of the addition of extra Minor Actinide (MA) isotopes from existing LWR stockpiles. In the presented work, up to 10% of the fuel was homogeneously replaced by an MA-mixture. The results are that addition of MA increases the potential of obtaining a closed fuel cycle. Reactivity coefficients generally decrease with increasing MA content. Addition of MA reduces the reactivity swing and allows very long irradiation intervals up to 10% FIMA with a small reactivity swing. Multirecycling studies show that a 600 MWth GCFR can transmute the MA from several PWRs. By a careful choice of the MA-fraction in the fuel, the reactivity of the fuel can be tuned to obtain a preset multiplication factor at end of cycle. Preliminary decay heat calculations show that the presence of MA in the fuel significantly increases the decay heat for time periods relevant to accidents (104–105s after shutdown). The paper ends with some recommendations for future research in this promising area of the nuclear fuel cycle.


2017 ◽  
Vol 153 ◽  
pp. 07034
Author(s):  
Mikhail Ternovykha ◽  
Georgy Tikhomirov ◽  
Yury Khomyakov ◽  
Igor Suslov

Author(s):  
Marco Ciotti ◽  
Jorge L. Manzano ◽  
Giacomo Grasso ◽  
Luigi Mansani ◽  
Carlo Petrovich

The electricity production systems, especially those based on nuclear fission, are increasingly facing more tight constraints and are subjected to more deep analyses based on the three aspects of economical sustainability, environmental sustainability and social sustainability. Nuclear Reactors future development has been outlined in the framework of the GIF (Generation IV International Forum), where the Lead Fast Reactor (LFR) is placed among the most promising innovative solutions. Many aspects of LFR offer a huge improvement from different points of view. The non pressurization of the system and the absence of sources of hazardous chemical potential energy enhances consistently its safety aspects, improving the perception of inherent safety of the Generation IV (G4) reactors in the public opinion. At the moment, due to the abundance of the new fossil resources, the competitiveness of Nuclear Power Plants is severely challenged, this aspect representing the most difficult to manage, besides the public acceptability. Moreover, for G4 reactors, an additional “cost premium” associated with the innovative technological concept has to be taken into account. Conversely, looking at the mid-term future, the real economical comparison has to be performed considering as competing sources, according to the IPCC recommendations and constraints enacted by the European Community, only CO2 free sources. In this context, economical competitiveness could be regained depending on the “cost premium” to be added to fossil fuels to become CO2 free, through the improvement of the carbon separation and storage techniques. The intrinsic lead properties (e.g.: low absorption cross section) permit to easily design LFR flexible cores, optimized with respect to a number of possible goals, as a long-lived core with minimal reactivity swing intended for battery concepts, or what is called an “adiabatic” core, where the entire Pu and MA inventory in the spent fuel can be indefinitely reused in a closed fuel cycle. The latter option allows to limit the waste throughput to the fission products only (along with the — unavoidable — losses from fuel reprocessing), and to benefit of natural resources minimization. These are both specific Generation IV goals envisioned to reach nuclear energy sustainability. An overall fuel cycle balance in a scenario with a step by step introduction of LFR reactors fleet grown in a specific geographical area, is in details analyzed in [1] and presented in this conference.


2009 ◽  
Vol 2009 ◽  
pp. 1-7 ◽  
Author(s):  
Richard Stainsby ◽  
Karen Peers ◽  
Colin Mitchell ◽  
Christian Poette ◽  
Konstantin Mikityuk ◽  
...  

Gas-cooled fast reactor (GFR) research is directed towards fulfilling the ambitious goals of Generation IV (Gen IV), that is, to develop a safe, sustainable, reliable, proliferation-resistant and economic nuclear energy system. The research is directed towards developing the GFR as an economic electricity generator, with good safety and sustainability characteristics. Fast reactors maximise the usefulness of uranium resources by breeding plutonium and can contribute to minimising both the quantity and radiotoxicity nuclear waste by actinide transmutation in a closed fuel cycle. Transmutation is particularly effective in the GFR core owing to its inherently hard neutron spectrum. Further, GFR is suitable for hydrogen production and process heat applications through its high core outlet temperature. As such GFR can inherit the non-electricity applications that will be developed for thermal high temperature reactors in a sustainable manner. The Euratom organisation provides a route by which researchers in all European states, and other non-European affiliates, can contribute to the Gen IV GFR system. This paper summarises the achievements of Euratom's research into the GFR system, starting with the 5th Framework programme (FP5) GCFR project in 2000, through FP6 (2005 to 2009) and looking ahead to the proposed activities within the 7th Framework Programme (FP7).


2021 ◽  
Vol 2072 (1) ◽  
pp. 012013
Author(s):  
F H Irka ◽  
Z Suud ◽  
D Irwanto ◽  
S N Khotimah ◽  
H Sekimoto

Abstract Gas-Cooled Fast Reactor-GFR is a Generation IV reactor that is helium-cooled and has a closed fuel cycle. Due to the target operation on 2022-2030, this reactor type still needs further research and development technologies. We investigated the neutronics performances of a GFR balance type core with some modification of CANDLE (Constant Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy production) burn-up scheme in the radial direction. The output power varied from 300 to 600 MWt. The neutronics calculation was performed using SRAC 2002 with JENDL 4.0 nuclear data library. The analysis indicate the reactor could operate critically for ten years without refueling with burn-up level 20% HM.


2009 ◽  
pp. 120-126
Author(s):  
K.V. Govindan Kutty ◽  
P.R. Vasudeva Rao ◽  
Baldev Raj

Atomic Energy ◽  
2021 ◽  
Author(s):  
N. V. Gorin ◽  
N. P. Voloshin ◽  
Yu. I. Churikov ◽  
A. N. Chebeskov ◽  
V. P. Kuchinov ◽  
...  

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