The U.S. accelerator transmutation of waste program

Beller, Denis; Tuyle, G.J. Van; Bennett, Deborah; Lawrence, G.P.; Thomas, Kimberly; Pasamehmetoglu, Kemal; Li, Ning; Hill, David; Laidler, J.J.; Fink, Phillip

doi:10.1016/s0168-9002(01)00163-2

Cited by 47 publications

(29 citation statements)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The angular distribution of D-T source neutrons, the microscopic differential cross section of the D-T reaction, and the energy angular distribution of D-T neutrons are plotted in Figures 35,36,and 37,respectively In the Monte Carlo calculations, D-T source neutrons have an isotropic distribution and 14.1 MeV energy. They are emitted from the copper disk surface facing the deuteron beam.…”

Section: C3 Deuterium-tritium Neutron Sourcementioning

confidence: 99%

“…In this project, water-moderated uranium-aluminum fuel plates have been coupled with an electron accelerator at Idaho State University in Pocatello, ID, USA. [36][37][38][39] In 2005, the International Atomic Energy Agency (IAEA) has started coordinated ADS research activities to validate computational methods, to characterize the performance of different subcritical systems, to develop and improve reactivity monitoring techniques, and the utilization of low enriched uranium instead of high enriched uranium in these systems. These activities include the YALINA booster and thermal subcritical experiments.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Deterministic and Monte Carlo modeling and analyses of YALINA-THERMAL subcritical assembly.

Talamo

Gohar

2010

View full text Add to dashboard Cite

Section: C3 Deuterium-tritium Neutron Sourcementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Deterministic and Monte Carlo modeling and analyses of YALINA-THERMAL subcritical assembly.

Talamo

Gohar

2010

View full text Add to dashboard Cite

“…A very promising way under investigation for the management of radioactive waste is the transmutation of long-lived radionuclides in a fast neutron nuclear reactor into shorter lived or stable ones [1][2][3]. Therefore, transmutation of long-lived nuclides has been investigated in various systems for characterisation of their nuclear data.…”

Section: Introductionmentioning

confidence: 99%

Accurate determination of Curium and Californium isotopic ratios by inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) in 248Cm samples for transmutation studies

Gourgiotis,

Isnard,

Aubert

et al. 2010

International Journal of Mass Spectrometry

View full text Add to dashboard Cite

46The French Atomic Energy Commission has carried out several experiments including the 47 mini-INCA (INcineration of Actinides) project for the study of minor-actinide transmutation 48 processes in high intensity thermal neutron fluxes, in view of proposing solutions to reduce 49 the radiotoxicity of long-lived nuclear wastes. In this context, a Cm sample enriched in 248 Cm 50 (~97 %) was irradiated in thermal neutron flux at the High Flux Reactor (HFR) of the Laue-51Langevin Institute (ILL). This work describes a quadrupole ICP-MS (ICP-QMS) analytical 52 procedure for precise and accurate isotopic composition determination of Cm before sample 53 irradiation and of Cm and Cf after sample irradiation. The factors that affect the accuracy and 54 reproducibility of isotopic ratio measurements by ICP-QMS, such as peak centre correction, 55 detector dead time, mass bias, abundance sensitivity and hydrides formation, instrumental 56 background, and memory blank were carefully evaluated and corrected. Uncertainties of the 57 isotopic ratios, taking into account internal precision of isotope ratio measurements, peak 58 tailing, and hydrides formations ranged from 0.3% to 1.3%. This uncertainties range is quite 59 acceptable for the nuclear data to be used in transmutation studies.

show abstract

“…Since a water-cooled reactor uses water near the fuel, it is feared that, if there is a breach, the water will dissolve the fuel and carry it into the environment. Sodium-cooled reactors, while limiting the potential for water contact with the fuel, also have a flaw in that carbides have shown to be sensitive to liquid sodium [27,15,35,29,6]. …”

Section: Carbides For Reactor Fuelmentioning

confidence: 99%

Radiation Damage and Fission Product Release in Zirconium Nitride

Egeland

2005

View full text Add to dashboard Cite

Zirconium nitride is a material of interest to the AFCI program due to some of its particular properties, such as its high melting point, strength and thermal conductivity. It is to be used as an inert matrix or diluent with a nuclear fuel based on transuranics. As such, it must sustain not only high temperatures, but also continuous irradiation from fission and decay products. This study addresses the issues of irradiation damage and fission product retention in zirconium nitride through an assessment of defects that are produced, how they react, and how predictions can be made as to the overall lifespan of the complete nuclear fuel package.Ion irradiation experiments are a standard method for producing radiation damage to a surface for observation. Cryogenic irradiations are performed to produce the maximum accumulation of defects, while elevated temperature irradiations may be used to allow defects to migrate and react to form clusters and loops. Cross-sectional transmission electron microscopy and grazing-incidence x-ray diffractometry were used in evaluating the effects that irradiation has on the crystal structure and microstructure of the material. Other techniques were employed to evaluate physical effects, such as nanoindentation and helium release measurements.Results of the irradiations showed that, at cryogenic temperatures, ZrN withstood over 200 displacements per atom without amorphization. No significant change to the lattice or microstructure was observed. At elevated temperatures, the large amount of damage showed mobility, but did not anneal significantly. Defect clustering was possibly observed, yet the size was too small to evaluate, and bubble formation was not observed.Defects, specifically nitrogen vacancies, affect the mechanical behavior of ZrN dramatically. Current and previous work on dislocations shows a distinct change in slip plane, which is evidence of the bonding characteristics. The stacking-fault energy changes dramatically with lowered nitrogen stoichiometry, resulting in widely spaced partial dislocations in ZrN with high nitrogen vacancy concentration.The wide range of nitrogen stoichiometry in the phase field shows that ZrN may accept nitrogen defects readily. Explanations for this are suggested based upon the bonding structure of these cubic nitrides. This structure allows for a solid framework to remain on one sublattice, while at the same time allowing defects on the other sublattice. This allowance for defects allows significant damage from irradiation yet also decreases the drive for cluster growth. This is evidence that the structure will be acceptable for long-term use as a nuclear reactor fuel.

show abstract

The U.S. accelerator transmutation of waste program

Cited by 47 publications

References 4 publications

Deterministic and Monte Carlo modeling and analyses of YALINA-THERMAL subcritical assembly.

Deterministic and Monte Carlo modeling and analyses of YALINA-THERMAL subcritical assembly.

Accurate determination of Curium and Californium isotopic ratios by inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) in 248Cm samples for transmutation studies

Radiation Damage and Fission Product Release in Zirconium Nitride

Contact Info

Product

Resources

About