Transition to thorium fuel cycle for TMSR

Zou, Chunyan; Cai, Cunlei; Yu, Chenggang; Wu, Jianhui; Chen, J.G.

doi:10.1016/j.nucengdes.2018.01.033

Cited by 53 publications

(25 citation statements)

References 17 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…For example, the idealized MSBR discussed above, which starts up with a HALEU core but only requires refueling with thorium afterward, is unphysical. Studies have found that an MSBR that starts up with HALEU instead of HEU or U-233-an essential nonproliferation requirement-would need to operate at least 20 years to reach a steady-state (Betzler, Powers, and Worrall 2017;Zou et al 2018 Protactinium and the Thorium Fuel Cycle neutron before decaying to U-233, it will become U-234, which is not useful for nuclear fuel. Because protactinium-233 has such a long half-life, there is a high likelihood if it stays in the reactor that it will absorb a neutron and thus will not decay to U-233, degrading the reactor's capability to breed new fuel.…”

Section: Technical Challe Ng Esmentioning

confidence: 99%

"Advanced" isn't Always Better: Assessing the Safety, Security, and Environmental Impacts of Non-Light-Water Nuclear Reactors

Lyman¹

2021

View full text Add to dashboard Cite

show abstract

Section: Technical Challe Ng Esmentioning

confidence: 99%

"Advanced" isn't Always Better: Assessing the Safety, Security, and Environmental Impacts of Non-Light-Water Nuclear Reactors

Lyman¹

2021

View full text Add to dashboard Cite

show abstract

“…With many remarkable characteristics such as inherent safety, excellent neutron economy, no fuel fabrication, online refueling and reprocessing, and so on, MSR can attain high burnup and is considered to have the ability to operate in a thorium–uranium fuel cycle and the potential to burn transuranic elements 16‐19 . Up to now, many different types of MSR have been designed to serve as the burner, converter, or breeder in any of the thermal, epithermal, or fast spectrum reactors using enriched U‐235, U‐233, or transuranic elements as the fissile fuel 20‐24 . In 2011, China initiated a pioneer program of research and development (R&D) for thorium‐based molten salt reactors (TMSRs) at the Shanghai Institute of Applied Physics, Chinese Academy of Science (SINAP, CAS) 25,26 .…”

Section: Introductionmentioning

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

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

“…The latter is not naturally occurring, since its half-life (160,000 years) is comparably shorter than the only naturally occurring fissile nuclide, 235 U (703.8 million years). However, MSR can be started by virtually any fissile isotope whilst gradually transition into pure thorium cycle [8]. This includes 235 U and 239 Pu.…”

Section: Introduction *mentioning

confidence: 99%

Investigation on Inherent Safety of One Fluid-Molten Salt Reactor (Of-Msr) With Various Starting Fuel

Dwijayanto

Hermawan

2020

Tri Dasa Mega

View full text Add to dashboard Cite

Molten salt reactor (MSR) is often associated with thorium fuel cycle, thanks to its excellent neutron economy and online reprocessing capability. However, since 233U, the fissile used in pure thorium fuel cycle, is not commercially available, the MSR must be started with other fissile nuclides. Different fissile yields different inherent safety characteristics, and thus must be assessed accordingly. This paper investigates the inherent safety aspects of one fluid MSR (OF-MSR) using various fissile fuel, namely low-enriched uranium (LEU), reactor grade plutonium (RGPu), and reactor grade plutonium + minor actinides (PuMA). The calculation was performed using MCNPX2.6.0 programme with ENDF/B-VII library. Parameters assessed are temperature coefficient of reactivity (TCR) and void coefficient of reactivity (VCR). The result shows that TCR for LEU, RGPu, and PuMA are -3.13 pcm, -2.02 pcm and -1.79 pcm, respectively. Meanwhile, the VCR is negative only for LEU, whilst RGPu and PuMA suffer from positive void reactivity. Therefore, for the OF-MSR design used in this study, LEU is the only safe option as OF-MSR starting fuel.Keywords: MSR, Temperature coefficient of reactivity, Void coefficient of reactivity, Low enriched uranium, Reactor grade plutonium, Minor actinides

show abstract

Transition to thorium fuel cycle for TMSR

Cited by 53 publications

References 17 publications

"Advanced" isn't Always Better: Assessing the Safety, Security, and Environmental Impacts of Non-Light-Water Nuclear Reactors

"Advanced" isn't Always Better: Assessing the Safety, Security, and Environmental Impacts of Non-Light-Water Nuclear Reactors

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

Investigation on Inherent Safety of One Fluid-Molten Salt Reactor (Of-Msr) With Various Starting Fuel

Contact Info

Product

Resources

About