Review of Transmutation Fuel Studies

Carmack, Jon; Pasamehmetoglu, Kemal

doi:10.2172/926357

Cited by 8 publications

(7 citation statements)

References 26 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Three different minor actinide loadings will be investigated (3% Am, 5% Am, and 2% Np-2% Am) [17]. The Am vector is following the same basic definitions as described for the Pu vector mentioned previously.…”

Section: Reference Systemmentioning

confidence: 99%

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Merk

2013

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

The use of fine distributed moderating material to enhance the feedback effects and to reduce the sodium void effecting SFRs is described. The drawback on the feedback effects due to the introduction of minor actinides into SFR fuel is analyzed. The possibility of compensation of the effect of the minor actinides on the feedback effects by the use of fine distributed moderating material is demonstrated. The consequences of the introduction of fine distributed moderating material into fuel assemblies with fuel configurations foreseen for minor actinide transmutation are analyzed, and the positive effects on the transmutation efficiency are shown. Finally, the possible increase of the Americium content to improve the transmutation efficiency is discussed, the limit value of Americium is determined, and the possibilities given by an increase of the hydrogen content are analyzed.

show abstract

Section: Reference Systemmentioning

confidence: 99%

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Merk

2013

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

show abstract

“…However, release fraction calculations for europium were not reported. 2.1.5.5 AFC Series PIE Lastly, recently a sequence of tests, known as the AFC series, have examined the performance of metal fuel using the Advanced Test Reactor (ATR) [33]. In particular, the AFC-1F, 1H, 2A, and 2B experiments investigated the behavior of a variety of metal fuel alloys of U, Pu, Np, Am, and Zr, at burnup ranges from several percent to greater than 25%.…”

Section: Fftf Piementioning

confidence: 99%

Regulatory Technology Development Plan - Sodium Fast Reactor. Mechanistic Source Term - Metal Fuel Radionuclide Release

Grabaskas

Bucknor

Jerden

2016

View full text Add to dashboard Cite

This analysis involves the examination of radionuclide release from metal fuel under conditions that would be typical of design basis and beyond design basis accidents for metal fuel, pool-type SFRs. This includes pin breach under normal operation due to defects, cladding failure at elevated temperatures due to eutectic penetration, and fuel melting conditions due to loss of heat sink/loss of flow scenarios or transient overpowers. Fuel conditions for accident scenarios that typically fall in the residual risk category or beyond for metal fuel, pool-type SFRs, such as core energetics, hypothetical core disruption accidents, or loss of sodium accidents, are not examined, as these accidents may involve very high fuel temperatures, and the possibility of fuel vaporization.Radionuclide release from metal fuel to the primary sodium is examined for fuel conditions typical of design basis and beyond design basis accidents at metal fuel, pool-type SFRs.

show abstract

“…The MA fuel composition was chosen to be MA-40Zr under the assumption that it would have similar properties as the Pu-40Zr and Pu-MA-40Zr fuels. Metal fuel samples of Pu-40Zr, Pu-12Am-40Zr and Pu-10Am-10Np-40Zr were irradiated in the Advanced Test Reactor and included in the Advanced Fuel Cycle irradiation test series to evaluate the effects caused by the existence of MAs (Carmack and Pasamehmetoglu, 2008;IAEA, 2010). Recent experimental results showed that the major irradiation performance variables of the metal fuel samples are similar to those of U-Zr and U-Pu-Zr fuels (Carmack and Pasamehmetoglu, 2008;IAEA, 2010), which are the startup and recycled fuel types of the first-stage FR of the two-stage fuel cycle option, respectively.…”

Section: Selection Of Moderator and Target Materialsmentioning

confidence: 99%

A moderated target design for minor actinide transmutation in sodium-cooled fast reactor

Park

Lin

Yang

2016

Annals of Nuclear Energy

View full text Add to dashboard Cite

This paper presents a moderated target assembly design study for minor actinide (MA) transmutation in the first-stage sodium-cooled fast reactor (FR) to reduce the amount of MA to be sent to the second-stage accelerator driven system (ADS) in a two-stage FR/ADS fuel cycle option. In order to minimize the local power peaking problem induced by moderated target assemblies, the target assemblies were loaded in the reflector region. Using MA-40Zr target composition and ZrH1.6 moderator, an optimum MA target assembly design was developed to maximize the MA destruction within the practical thermal design limits on the cladding inner wall temperature. Long-lived fission product pins were used as thermal neutron filters to reduce the local power peaking in the adjacent fuel assemblies due to the thermal neutron leakage from the moderated target assembly. The performance characteristics of the FR with moderated target assemblies were evaluated by performing detailed neutronics and thermal-hydraulics analyses.Analysis results showed that the use of MA target assemblies reduces the amount of MA to be sent to ADS by a factor of six without deteriorating safety characteristics. As a result, the electricity sharing of ADS in a nuclear park composed of FRs and ADSs was reduced to 0.3% from 1.9%.

show abstract

Review of Transmutation Fuel Studies

Cited by 8 publications

References 26 publications

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Regulatory Technology Development Plan - Sodium Fast Reactor. Mechanistic Source Term - Metal Fuel Radionuclide Release

A moderated target design for minor actinide transmutation in sodium-cooled fast reactor

Contact Info

Product

Resources

About