Prospects of subcritical molten salt reactor for minor actinides incineration in closed fuel cycle

Kerntechnik ◽  
2015 ◽  
Vol 80 (4) ◽  
pp. 389-393 ◽  
Author(s):  
P. N. Alekseev ◽  
A. L. Balanin ◽  
V. Yu. Blandinsky ◽  
A. A. Dudnikov ◽  
P. A. Fomichenko ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Minor Actinides ◽  
Molten Salt Reactor ◽  
Closed Fuel Cycle

scholarly journals INVESTIGATION ON INHERENT SAFETY OF ONE FLUID-MOLTEN SALT REACTOR (OF-MSR) WITH VARIOUS STARTING FUEL

2020 ◽  
Vol 22 (2) ◽  
pp. 54
Author(s):  
R. Andika Putra Dwijayanto ◽  
Dedy Prasetyo Hermawan
Keyword(s):  
Molten Salt ◽  
Temperature Coefficient ◽  
Fuel Cycle ◽  
Minor Actinides ◽  
Molten Salt Reactor ◽  
Inherent Safety ◽  
Safety Aspects ◽  
Safe Option ◽  
Enriched Uranium ◽  
Coefficient Of Reactivity

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

Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium

2022 ◽  
Vol 165 ◽  
pp. 108638
Author(s):  
Jianhui Wu ◽  
Jingen Chen ◽  
Chunyan Zou ◽  
Chenggang Yu ◽  
Xiangzhou Cai ◽  
...  
Keyword(s):  
Molten Salt ◽  
Heavy Water ◽  
Fuel Cycle ◽  
Molten Salt Reactor

Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning

2014 ◽  
Author(s):  
Jiři Křepel ◽  
Valentyn Bykov ◽  
Konstantin Mikityuk ◽  
Boris Hombourger ◽  
Carlo Fiorina ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Ex Situ ◽  
Molten Salt Reactor ◽  
Inherent Safety ◽  
Neutron Spectra ◽  
Fuel Fabrication

The Molten Salt Reactor (MSR) represents an old concept, but its properties are qualifying it for the advanced utilization: inherent safety, excellent neutron economy, possibility of continuous or batch reprocessing without fuel fabrication. The aim of this paper is to characterize the MSR unique fuel cycle advantages in different neutron spectra using the results of ERANOS-based EQL3D and ECCO-MATLAB based EQL0D procedures. It also focuses on the low production of higher actinides in the Th-U cycle and based on the results, it proposes a simplified in situ recycling of the fuel and the delayed ex situ carrier salt cleaning or direct disposal by vitrification.

Molten-Salt Reactor for Nuclear Fuel Cycle Closure on All Actinides

Atomic Energy ◽  
2019 ◽  
Vol 125 (5) ◽  
pp. 279-283 ◽  
Author(s):  
V. V. Ignatiev ◽  
M. V. Kormilitsyn ◽  
L. A. Kormilitsyna ◽  
Yu. M. Semchenkov ◽  
Yu. S. Fedorov ◽  
...  
Keyword(s):  
Molten Salt ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Molten Salt Reactor

Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium

2018 ◽  
Vol 104 ◽  
pp. 75-84 ◽  
Author(s):  
D.Y. Cui ◽  
X.X. Li ◽  
S.P. Xia ◽  
X.C. Zhao ◽  
C.G. Yu ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Molten Salt Reactor ◽  
Enriched Uranium

scholarly journals Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor

2017 ◽  
Author(s):  
Benjamin R. Betzler ◽  
Jeffrey J. Powers ◽  
Andrew Worrall ◽  
Sean Robertson ◽  
Leslie Dewan ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Molten Salt Reactor ◽  
Two Dimensional ◽  
Fuel Cycle Analysis

scholarly journals Thorium Fuel Cycle for a Molten Salt Reactor: State of Missouri Feasibility Study

2020 ◽  
Author(s):  
Yoonjo Lee ◽  
Matthew Simones ◽  
John Kennedy ◽  
Hakan Us ◽  
Philip Makarewicz ◽  
...  
Keyword(s):  
Molten Salt ◽  
Feasibility Study ◽  
Fuel Cycle ◽  
Molten Salt Reactor

scholarly journals SIMULATION OF BREED AND BURN FUEL CYCLE OPERATION OF MOLTEN SALT REACTOR IN BATCH-WISE REFUELING MODE

2021 ◽  
Vol 247 ◽  
pp. 13003
Author(s):  
Valeria Raffuzzi ◽  
Jiri Krepel
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Fission Products ◽  
Molten Salt Reactor ◽  
Core Size ◽  
Spent Fuel ◽  
Fluid Core ◽  
Active Core ◽  
Breed And Burn ◽  
Gen Iv

The Molten Salt Reactor (MSR) is one of the most revolutionary Gen-IV reactors and it can be operated, especially with chloride salts, in the so-called breed and burn fuel cycle. In this type of fuel cycle the fissile isotopes from spent fuel do not need to be reprocessed, because the excess bred fuel covers the losses. The liquid phase of the MSR fuel assures its instant homogenization, and the reactor can be operated with batch-wise refueling thus reaching an equilibrium state. At the same time, the active core of the chloride fast MSR needs to be bulky to limit neutron leakage. In this study, the code Serpent 2 was coupled to the Python script BBP to simulate batch-wise operation of the breed and burn MSR fuel cycle. The script, previously developed for solid assemblies shuffling, was modified to simulate fuel homogenization after fertile material addition. Several fuel salts and fission products removal strategies were simulated and their impact was analyzed. Similarly, the influence of blanket volume was assessed in a two-fluid core layout. The results showed that the reactivity initially grows during the irradiation period and later decreases. The blanket has a large impact on the performance and it can be used to further increase the fuel burnup or to shrink the active core size. The breed and burn fuel cycle in MSR can reach high fuel utilization without fuel reprocessing and a multi-fluid layout can help to decrease the core size.

scholarly journals An optimization methodology for heterogeneous minor actinides transmutation

2018 ◽  
Vol 4 ◽  
pp. 4
Author(s):  
Timothée Kooyman ◽  
Laurent Buiron ◽  
Gérald Rimpault
Keyword(s):  
Fuel Cycle ◽  
Volume Fraction ◽  
Negative Impact ◽  
Positive Impact ◽  
Optimal Solution ◽  
Minor Actinides ◽  
Spent Fuel ◽  
Closed Fuel Cycle ◽  
Decay Heat ◽  
The Core

In the case of a closed fuel cycle, minor actinides transmutation can lead to a strong reduction in spent fuel radiotoxicity and decay heat. In the heterogeneous approach, minor actinides are loaded in dedicated targets located at the core periphery so that long-lived minor actinides undergo fission and are turned in shorter-lived fission products. However, such targets require a specific design process due to high helium production in the fuel, high flux gradient at the core periphery and low power production. Additionally, the targets are generally manufactured with a high content in minor actinides in order to compensate for the low flux level at the core periphery. This leads to negative impacts on the fuel cycle in terms of neutron source and decay heat of the irradiated targets, which penalize their handling and reprocessing. In this paper, a simplified methodology for the design of targets is coupled with a method for the optimization of transmutation which takes into account both transmutation performances and fuel cycle impacts. The uncertainties and performances of this methodology are evaluated and shown to be sufficient to carry out scoping studies. An illustration is then made by considering the use of moderating material in the targets, which has a positive impact on the minor actinides consumption but a negative impact both on fuel cycle constraints (higher decay heat and neutron) and on assembly design (higher helium production and lower fuel volume fraction). It is shown that the use of moderating material is an optimal solution of the transmutation problem with regards to consumption and fuel cycle impacts, even when taking geometrical design considerations into account.

scholarly journals Fuel cycle and neutronic performance of a spectral shift molten salt reactor design

2018 ◽  
Vol 119 ◽  
pp. 396-410 ◽  
Author(s):  
Benjamin R. Betzler ◽  
Sean Robertson ◽  
Eva E. Davidson (née Sunny) ◽  
Jeffrey J. Powers ◽  
Andrew Worrall ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Reactor Design ◽  
Spectral Shift ◽  
Molten Salt Reactor ◽  
Neutronic Performance
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