Long-Lived Waste Transmutation in Reactors

Tommasi, J.; Delpech, Marc; Grouiller, Jean-Paul; Zaetta, Alain

doi:10.13182/nt111-133

Cited by 71 publications

(23 citation statements)

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“…A few studies have stated that a given fixed concentration of about 2% is acceptable in large sodium cooled fast reactors (SFRs) with oxide fuel [4,5], albeit without a proper transient analysis to back up the claim.…”

Section: Impact On Transient Behaviourmentioning

confidence: 99%

Physics of Americium Transmutation

Wallenius¹

2012

Nuclear Engineering and Technology

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Section: Impact On Transient Behaviourmentioning

confidence: 99%

Physics of Americium Transmutation

Wallenius¹

2012

Nuclear Engineering and Technology

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“…and fission products are considered as waste and discarded during the reprocessing step. Np was not accounted for here but it can be safely assumed that it could follow the same flowsheet as Pu [10].…”

Section: Description Of the Optimization Processmentioning

confidence: 99%

An optimization methodology for heterogeneous minor actinides transmutation

Kooyman

Buiron

Rimpault

2018

EPJ Nuclear Sci. Technol.

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In the case of a closed fuel cycle, minor actinides transmutation can lead to a strong reduction in spent fuel radiotoxicity and decay heat. In the heterogeneous approach, minor actinides are loaded in dedicated targets located at the core periphery so that long-lived minor actinides undergo fission and are turned in shorter-lived fission products. However, such targets require a specific design process due to high helium production in the fuel, high flux gradient at the core periphery and low power production. Additionally, the targets are generally manufactured with a high content in minor actinides in order to compensate for the low flux level at the core periphery. This leads to negative impacts on the fuel cycle in terms of neutron source and decay heat of the irradiated targets, which penalize their handling and reprocessing. In this paper, a simplified methodology for the design of targets is coupled with a method for the optimization of transmutation which takes into account both transmutation performances and fuel cycle impacts. The uncertainties and performances of this methodology are evaluated and shown to be sufficient to carry out scoping studies. An illustration is then made by considering the use of moderating material in the targets, which has a positive impact on the minor actinides consumption but a negative impact both on fuel cycle constraints (higher decay heat and neutron) and on assembly design (higher helium production and lower fuel volume fraction). It is shown that the use of moderating material is an optimal solution of the transmutation problem with regards to consumption and fuel cycle impacts, even when taking geometrical design considerations into account.

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“…Comparing the results for the candidate TID GFR with those of a PWR [Tommasi et al, 1995] and LFR [Todreas and Hejzlar, 2007], Table 8.5 shows that the candidate GFR performs much better than the PWR with respect to Pu and MA production (not to be confused with inventory, which of course is much larger). In fact, the GFR has a net MA destruction rate, due mainly to its ability to transmute Np-237 and Am-241, as shown in Table 8.4.…”

Section: Maitru Management Of Tid Corementioning

confidence: 99%

Optimized Core Design of a Supercritical Carbon Dioxide-Cooled Fast Reactor

2008

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Spurred by the renewed interest in nuclear power, Gas-cooled Fast Reactors (GFRs) have received increasing attention in the past decade. Motivated by the goals of the Generation-IV International Forum (GIF), a GFR cooled by supercritical carbon dioxide (S-CO 2 ), fueled with Light Water Reactor spent fuel transuranics, and directly coupled with a Brayton cycle is under investigation as part of a larger research effort at MIT. While the original GFR chosen by the GIF is a 600MWh version using Helium as a coolant, the work presented here is for a 2400 MWd, core using S-CO 2 as a coolant, which has comparable thermal efficiency (-45%) at much lower temperatures (650"C v. 850 0 C) A reactor core for use in this direct cycle S-CO 2 GFR has been designed which satisfies established neutronic and thermal-hydraulic steady state design criteria, while concurrently supporting the Gen-IV criteria of sustainability, safety, proliferation, and economics. Use of innovative Tube-in-Duct (TID) fuel has been central to accomplishing this objective, as it provides a higher fuel volume fraction and lower fuel temperatures and pressure drop when compared to traditional pin-type fuel. Further, this large fuel volume fraction allows for a large enough heavy metal loading for a sustainable core lifetime without the need for external blankets, enhancing the proliferation resistance of such an approach.Use of Beryllium Oxide (BeO) as a diluent is explored as a means for both power shaping and coolant void reactivity (CVR) reduction in fast reactors. Results show that relatively flat power profiles can be maintained throughout a batch-loaded "battery" core life using a combination of enrichment and diluent zoning, due to the slight moderating effect of the BeO. Combining BeO diluent with the innovative strategy of using a thick volume of S-CO 2 coolant as the radial reflector yields negative CVR values throughout core life, a rare, if not unique accomplishment for fast reactors. The ability to maintain negative CVR comes from a combination of the effects of spectral softening due to the BeO diluent and the enhanced leakage upon voiding of the S-CO 2 radial reflector.In support of assessing the neutronic self-controllability of this core, a simple first-order steady state design metric is developed, modified from other established methodology to suit the uniqueness of this core concept. The results of this analysis show that the core will passively shut itself down without violation of established core thermal limits in the event of several limiting Anticipated Transients Without SCRAM (ATWS) scenarios, except for a Loss of Coolant Without SCRAM at End of Core life. Since most of the requisites for passive core shutdown have been demonstrated within the parameter uncertainties of current estimates, the candidate core design is deemed sufficiently safe. Further, design solutions for fixing this deficiency are proposed.Alternative cores using traditional pin-type fuel and innovative Internally-Cooled Annular Fuel (ICAF) have also be...

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Long-Lived Waste Transmutation in Reactors

Cited by 71 publications

References 0 publications

Physics of Americium Transmutation

Physics of Americium Transmutation

An optimization methodology for heterogeneous minor actinides transmutation

Optimized Core Design of a Supercritical Carbon Dioxide-Cooled Fast Reactor

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