Assessment of the Neutronic and Fuel Cycle Performance of the Transatomic Power Molten Salt Reactor Design

2017 ◽  
Author(s):  
Sean Robertson ◽  
Leslie Dewan ◽  
Mark Massie ◽  
Eva E. Davidson ◽  
Benjamin R. Betzler ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Reactor Design ◽  
Cycle Performance ◽  
Molten Salt Reactor

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

scholarly journals Fuel Cycle Performance of Fast Spectrum Molten Salt Reactor Designs

2019 ◽  
Author(s):  
Andrei Rykhlevskii ◽  
Benjamin R. Betzler ◽  
Jin Whan Bae ◽  
Kathryn Huff
Keyword(s):  
Performance Analysis ◽  
Molten Salt ◽  
Doubling Time ◽  
Fuel Cycle ◽  
Cycle Performance ◽  
Simplified Model ◽  
Molten Salt Reactor ◽  
Cell Models ◽  
Breeding Ratio ◽  
Full Core

4 fast-spectrum molten salt conceptual designs have been selected for fuel cycle performance analysis. 3D full core and 2D unit cell models have been developed to justify the possibility to use a simplified model for computational-heavy depletion simulation with truly continuous online reprocessing. Finally, 60-years depletion simulation for Molten Salt Fast Reactor (MSFR) shown lifetime breeding ratio 1.0072 and doubling time 139 years in Th/U fuel cycle.

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

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

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 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

Sign in / Sign up

Export Citation Format

Share Document