Development of a fissile particle for HTGR fuel recycle

Homan, F.J.; Long, E.L.; Lindemer, T.B.; Beatty, R.L.; Tiegs, T.N.

doi:10.2172/7129426

Cited by 4 publications

(5 citation statements)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The postirradiation heating tests were conducted at temperatures of 1473, 1623, and 1773 K for more than 36 Ms (10 000 h). 68 Likewise, the addition of the ZrC oxygen getter in the UO 2 fuel types accomplishes the same purpose, while also allowing much higher retention of Eu in the pure oxide kernels. There was significant release of silver and europium from the TRISO-coated UO 2 particles with ZrC dispersed in the buffer layer under the same conditions, as well as from the ordinary TRISO-coated UO 2 , UC 2 , and mixed UO 2 -UC 2 fuels.…”

Section: Retention Of Fission Productsmentioning

confidence: 98%

“…The inventories of fission products in the sample particles were measured before and after the heating experiment and the released ones collected on sleeves were measured at certain time intervals by g-ray spectrometer. 68,69 Gas pressures in such particles will certainly be reduced compared to those in pure UO 2 fuel, and UCO fuel kernels should retain all the rare earths, other than Eu, well. 19,20 The TRISO-coated UO 2 particles gettered with a solid ZrC overcoating on the kernel did not release any measurable fission products during postirradiation annealing at 1773 K for over 42 Ms ($12 000 h).…”

Section: Retention Of Fission Productsmentioning

confidence: 99%

“…68,69,81 Lanthanide is kept as a stable oxide within the oxide and oxycarbide (O/U > 1.1) fuel kernels. 68,69,81 Lanthanide is kept as a stable oxide within the oxide and oxycarbide (O/U > 1.1) fuel kernels.…”

Section: Designs Of Sic-containing Triso-coated Particle Fuelmentioning

confidence: 99%

See 2 more Smart Citations

Advanced Concepts in TRISO Fuel

Minato

Ogawa

2012

Comprehensive Nuclear Materials

View full text Add to dashboard Cite

Section: Retention Of Fission Productsmentioning

confidence: 98%

Section: Retention Of Fission Productsmentioning

confidence: 99%

See 1 more Smart Citation

Advanced Concepts in TRISO Fuel

Minato

Ogawa

2012

Comprehensive Nuclear Materials

View full text Add to dashboard Cite

“…Originally, HTGR fissile fuel was chemically either oxide or dicarbide, but each composition had drawbacks during reactor operation: the oxide suffered from kernel migration ("amoeba effect"), while the carbide gave enhanced attack of fission products on the kernel coating. A theoretical analysis of the mechanisms and controlling kinetics suggested that a mixture of uranium oxide and carbide would minimize both problems, and this was subsequently verified by irradiation tests [4,5], Uranium-loaded resin provided a natural pathway to this composition and also utilized a simpler process than did the gel methods. In addition, the resin process yielded a product with retained porosity which has potential advantages relative to coating.…”

Section: Introductionmentioning

confidence: 93%

The Preparation of HTGR Fissile Fuel Kernels by Uranium-Loading of Ion Exchange Resins

Notz

Shaffer

1978

Radiochimica Acta

View full text Add to dashboard Cite

Resin loading ¡Ion exchange resin/ HTGR fissile fuel / Nuclear fuel kernels / Uranium loading /Weak-acid resinAbstract Fissile fuel for High-Temperature Gas-Cooled Reactors (HTGRs) is fabricated in the form of small spheres ~300 um in diameter, each containing ~ 70 Mg of highly enriched uranium; the preferred chemical composition is a mixture of oxide and carbide. This report describes a process for loading weakacid ion exchange resin beads with uranium, from which the desired product is then derived by thermal treatment. The resin loading process has a major advantage over alternative, traditional methods because the process steps are relatively simple. This derives primarily from the fact that the resin is commercially available in the form of spherical beads. This factor is of significant benefit under any circumstances but especially in the case of the remote fabrication required for the highly radioactive 2 33 U recycle fuel. The process is based on the exchange of uranyl ion with the acid form of a carboxylate resin. This type and form of resin was chosen because (a) it contains only C, H, and O and is therefore free of other cations and additional undesirable elements such as N, S, or P; (b) it is available with a high enough concentration of exchange sites to achieve the necessary uranium density in the product. This usage differs from the usual applications of ion exchange resins because full loading is required, and the loaded resin itself is the desired product. In order to drive the reaction to essential completion, it is necessary to use acid-deficient uranyl nitrate [i. e., a composition equivalent to UO2(NO 3 ) 1-s (OH) 0 5 ]. This solution composition can be achieved either by extraction of HNOj with an amine in an organic solvent or by reaction with U0 3 . Each of these methods has been demonstrated in both batch and continuous modes. For recycle fuel, where uranyl nitrate solution is the natural product of reprocessing, amine extraction is preferred. For smaller operations, batch loading is the simpler approach; however, for larger operations, a single Higgins-type pulsed column can load 100 kg U per day in a continuous mode.

show abstract

“…Kernel migration is discussed in greater details in Refs. [33][34][35][36]44] and on pp. 2-33 to 2-43 in Ref.…”

Section: Elimination Of Kernel Migrationmentioning

confidence: 99%

Performance modeling of Deep Burn TRISO fuel using ZrC as a load-bearing layer and an oxygen getter

Wongsawaeng

2010

Journal of Nuclear Materials

View full text Add to dashboard Cite

Development of a fissile particle for HTGR fuel recycle

Abstract: NOTICE This document contains information of a preliminary nature. It is subject to revision or correction and therefore does not represent a final report.

Cited by 4 publications

References 11 publications

Advanced Concepts in TRISO Fuel

Advanced Concepts in TRISO Fuel

The Preparation of HTGR Fissile Fuel Kernels by Uranium-Loading of Ion Exchange Resins

Performance modeling of Deep Burn TRISO fuel using ZrC as a load-bearing layer and an oxygen getter

Contact Info

Product

Resources

About