Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor

Yu, Chenggang; Li, X.X.; Xiang-Zhou, Cai; Zou, Chunyan; Ma, Yuanwei; Wu, Jianhui; Han, Jianlong; Chen, Jingen

doi:10.1016/j.anucene.2016.09.025

Cited by 45 publications

(19 citation statements)

References 32 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The proportionality constant "k" was obtained from the comparison of the p(CsI) 2 /p(Cs 2 I 2 ) ratio with reported equilibrium constant for 2CsI(g)=Cs 2 I 2 (g) from thermodynamic database as equation (2) [12,14]. The Open Access Journal of Science and Technology In this study, the value of p(CsI) 2 /k 2 and p(Cs 2 I 2 )/k were obtained from measurement, therefore k was calculated.…”

Section: Methodsmentioning

confidence: 99%

See 1 more Smart Citation

The Evaporation Behavior of Volatile Fission Products in FLiNaK Salt

Taira¹,

Arita²,

Yamawaki³

2017

oajost

View full text Add to dashboard Cite

Molten salt reactor (MSR) was suggested for the one of the nuclear power plant concepts planned for generation IV. However, little study had been done on the severe accident at MSR. The one of the severe accident at MSR is considered that the molten salt with fuel will be exposed to air and some fission products will release to environment. The molten FLiNaK salt (LiF-NaF-KF: 46.5-11.5-42 mol%) with CsI(FLiNaK-CsI : 99-1 mol%) was evaporated and released gases were measured by mass spectrometry. The evaporated gases from above sample were mainly CsI and KI. The value of vapor pressure for CsI was low about ten to the first ∼ second power of vapor pressure for pure CsI at same temperature. Therefore, it is expected that FLiNaK prevents the release of CsI. On the other hand, despite KI were not included in original sample, KI released significantly.

show abstract

Section: Methodsmentioning

confidence: 99%

“…FLiNaK is one of the candidates which expected as a coolant or fuel solvent in MSFRs [11]. Primary loop is often used FLiBe (LiF -BeF 2 ) in many concept, in the other hand some design uses FLiNaK for primary loop [12]. The properties of FLiNaK are indicated in Table 2.…”

Section: Introductionmentioning

confidence: 99%

The Evaporation Behavior of Volatile Fission Products in FLiNaK Salt

Taira¹,

Arita²,

Yamawaki³

2017

oajost

View full text Add to dashboard Cite

show abstract

“…Benefiting a large amount of MAs in the Flinak salt, case 2 has a higher STC of about 366 kg/GWth.yr. The optimal STC and TR of MA for a 500 MWth molten salt fast reactor (MSFR) are about 363 kg/GWth.yr and 82.6%, respectively 50 . It can be said that the MA transmutation capability in a thermal spectrum TMSR is comparable to that in a fast spectrum TMSR, which demonstrates that it is also feasible for MA transmutation in a thermal TMSR.…”

Section: Resultsmentioning

confidence: 99%

Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors

Zou

et al. 2021

Int J Energy Res

Self Cite

View full text Add to dashboard Cite

Summary Transmutation of minor actinides (MAs) is an effective solution to reduce the long‐term radiotoxicity of nuclear waste. Online refueling and no fuel rod fabrication in thorium‐based molten salt reactors (TMSR) are two remarkable advantages of MA transmutation. However, MA solubility limit of the fuel salt and the neutron spectrum in the core are two key parameters that have a strong impact on MA transmutation capability. In this paper, three types of carrier salt with different MA solubility limits and various salt volume fractions (SVFs) are introduced in a TMSR core to evaluate the MA transmutation characteristics. The results indicate that the Flibe salt with the best neutron economy can obtain the highest MA transmutation rate (TR), while the Flinak salt with the largest MA inventory can achieve the highest specific MA transmutation consumption (STC). STC and TR for the case with the Flibe salt and 5% SVF are about 200 kg/GWth.yr and 82%, respectively, which indicates that it can consume the annual MA yields from about 3.37 typical pressurized water reactors (PWRs). Meanwhile, the STC and TR for the case with the Flinak salt and 40% SVF are about 366 kg/GWth.yr and 75%, respectively, which indicates that it can consume the annual MA yields from about 50 typical PWRs. In addition, the total radiotoxicity of MAs after 50‐year operation in TMSR can be lowered by as high as about 50%. The significant production of Pu isotopes can be reused as nuclear fuel in fast reactors. In particular, Pu‐238, with the mass fraction of more than 60% in Pu isotopes, is a useful material for many nuclear applications. In conclusion, it is feasible to transmute MAs in TMSR and thus achieve the goals of reduction of MA's long‐term radioactive hazards.

show abstract

Section: Resultsmentioning

confidence: 99%

“…The high level radioactive TRU is stored temporarily in the reprocessing factory for both the batch and online reprocessing modes, which could be transmuted by a MSFR in the future. 36,41 The soluble FPs separated from the fuel salt are disposed directly. It should be noted that both gaseous and noble metallic FPs (Kr, Xe, Tc, Ru, etc) for the above fuel cycle modes can be removed online through a helium bubbling system during operation since it has been proved in the MSRE.…”

Section: Progressive Fuel Cycle Modes In Smmsrmentioning

confidence: 99%

Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes

Zou

et al. 2019

Int J Energy Res

Self Cite

View full text Add to dashboard Cite

Summary The thorium‐uranium (Th‐U) fuel cycle is considered as a potential approach to ensure a long‐term supply of nuclear fuel. Small modular molten salt reactor (SMMSR) is regarded as one of the candidate reactors for Th utilization, since it inherits the merits of both MSR and small modular reactor. The Th utilization in a 220‐MWe SMMSR with the once‐through fuel cycle mode is investigated first. Then, the SMMSR with batch and online fuel processing modes is investigated second for comparison, considering the progressive development of fuel reprocessing technology. To keep a negative temperature reactivity feedback coefficient (TRC), a configuration for fuel salt volume fraction (SVF) equal to 15%, with a mixed fuel of low enriched uranium (LEU) and thorium at an operation time of 5 years is recommended for the once‐through mode, corresponding to the Th energy contribution (ThEC) of 37.6% and natural U and Th utilization efficiency (UE) of 0.51%. Considering the solubility limit of heavy nuclide (HN) proportion (below 18.0 mol%) in the fuel salt, the total operation time of the SMMSR shall be less than 50 years for the batch reprocessing mode with a 5‐year reprocessing interval time. In this case, the ThEC and UE can be improved to about 47.4% and 0.99%, respectively. Finally, the Th utilization and fuel sustainability are analyzed at a lifetime of 50 years for the online reprocessing fuel cycle mode, including both the only online fission products (FPs) removing scheme and the fuel transition scheme from LEU to 233U. For the former scheme, the ThEC and UE can be further improved to 58.6% and 1.52%, respectively. For the latter scheme, 233Pa is extracted continuously from the core to breed and store 233U. If a total reactor lifetime of 50 years is assumed, the operation time using LEU as starting and feeding fuel for 6 years is required, and the bred 233U during this 6‐year operation can start and maintain the reactor criticality for the remaining 44 years. In this case, the ThEC is improved significantly to 89.1% corresponding to a UE of 2.74%.

show abstract

Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor

Cited by 45 publications

References 32 publications

The Evaporation Behavior of Volatile Fission Products in FLiNaK Salt

The Evaporation Behavior of Volatile Fission Products in FLiNaK Salt

Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors

Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes

Contact Info

Product

Resources

About