scholarly journals Thermochemical and transport properties important to molten salt reactor operation: Off-gas performance and the fission product mechanistic source term

2018 ◽  
Author(s):  
Joanna McFarlane ◽  
Charles F. Weber ◽  
Michael Scott Greenwood ◽  
A. L. Qualls
Keyword(s):  
Fission Product ◽  
Molten Salt ◽  
Transport Properties ◽  
Source Term ◽  
Molten Salt Reactor ◽  
Reactor Operation

Distribution and behavior of fission product 95Nb in FLiBe salt

2021 ◽  
Vol 0 (0) ◽  
Author(s):  
Zhiqiang Cheng ◽  
Xiaohe Wang ◽  
Zhongqi Zhao ◽  
Junxia Geng ◽  
Jifeng Hu ◽  
...  
Keyword(s):  
Fission Product ◽  
Redox Potential ◽  
Molten Salt ◽  
Molten Salt Reactor ◽  
Lithium Metal ◽  
Site Monitoring ◽  
Salt Addition ◽  
Redox Indicator ◽  
Γ Ray ◽  
And Behavior

Abstract The 235,238UF4 was irradiated by photo-neutrons, distribution and behavior of the fission product 95Nb from irradiated 235,238UF4 in FLiBe salt were investigated by the measurement of its activity in the salt with the γ-ray spectroscopy. The experiments indicated that a part of 95Nb deposited on the surfaces of graphite and Hastelloy, as the moderator and the structural materials of molten salt reactor (MSR), respectively, and the majority of 95Nb maintained in molten salt. Addition of lithium metal made 95Nb in salt to be reduced and settled, leading to the decrease in its activity. Degree of the decrease was found to be correlated with niobium concentration. The experimental results supported the statement proposed early by ORNL, that 95Nb might be used as a redox indicator for MSR. Finally, the problem met with on-site monitoring for redox potential in MSR was pointed, and a possible protocol to resolve the problem was proposed.

scholarly journals Fission product behavior in the Molten Salt Reactor Experiment

1975 ◽  
Author(s):  
E Compere ◽  
S Kirslis ◽  
E Bohlmann ◽  
F Blankenship ◽  
W Grimes
Keyword(s):  
Fission Product ◽  
Molten Salt ◽  
Molten Salt Reactor ◽  
Reactor Experiment

scholarly journals Study on the Ability of PCMSR to Produce Valuable Isotopes as a By Product of Energy Generation

2018 ◽  
Vol 3 (1) ◽  
pp. 7-14
Author(s):  
Andang Widiharto
Keyword(s):  
Fission Product ◽  
Molten Salt ◽  
Nuclear Reactor ◽  
Thermal Power ◽  
Processing System ◽  
Quasi Equilibrium ◽  
Molten Salt Reactor ◽  
Liquid Form ◽  
Fuel Processing ◽  
On Line

PCMSR (Passive Compact Molten Salt Reactor) is a variant of MSR (Molten Salt Reactor) type reactors. The MSR is one type of the Advanced Nuclear Reactor types. PCMSR uses mixtures of fluoride salt if the liquid form is in a high temperature operation. The use of liquid salt fuel allows the application of on line fuel processing system. The on line fuel processing system allows extraction of several valuable fission product isotopes such as Mo-99, Cs-137, Sr-89 etc. The capability of MSR to produce several valuable isotopes has been studied. This study is based on a denaturized breeder MSR design with 920 MWth of thermal power and 500 MWe of electrical output power with the thermal efficiency of 55 %. The initial composition of fuel salt is 70 % of a mole of LiF, 24 % of a mole of 232ThF4, 6 % of a mole of UF4. The enrichment level of U is 20 % of a mole of  U-235. The study is performed by a numerical calculation to solve a set of differential equations of fission product balance. This calculation calculates fission product generation due to fission reaction, precursor decay, and fission product annihilation due to decay, neutron absorption, and extraction. The calculation result shows that in quasi equilibrium conditions, the reactor can produce several valuable isotopes in substantially sufficient quantities, those are  Sr-89 (0.3 kCi/MWth/day, Sr-90 (1,91 Ci/MWth/day), Mo-99 (1.7 kCi/MWth/day), I-131 (0.42 kCi/MWth/day), I-132 (0.782 kCi/MWth/day), I-133 (1.12 kCi/MWth/day), Xe-133 (11.8 Ci/MWth/day), Cs-134 (39.3 mCi/MWth/day), Cs-137 (2.32 Ci/MWth/day) and La-140 (1.05 kCi/MWth/day).

scholarly journals Study on Kinetic Characteristics of Krypton and Xenon radioactive source term in molten salt reactor

2020 ◽  
Vol 239 ◽  
pp. 22005
Author(s):  
Bo Zhou ◽  
Rui Yan ◽  
Xiaohan Yu ◽  
Yang Zou ◽  
Shihe Yu ◽  
...  
Keyword(s):  
Numerical Simulation ◽  
Molten Salt ◽  
Source Term ◽  
Exhaust System ◽  
Simulation Method ◽  
Total Activity ◽  
Loop System ◽  
Molten Salt Reactor ◽  
Primary Loop ◽  
Accident Conditions

A numerical simulation program for the dynamic distribution of krypton and xenon with flow and on-line removal function was established for primary loop system of molten salt reactor(MSR) Based on Mathe-matica7.0.The simulation results of the static burnup was compared with ORIGEN-S program, and the deviation is less than 10%, which is in good agreement.The distribution and dynamic characteristics of krypton and xenon in the primary loop system were analyzed under the flow regionalization and online removal model.The results show that,the static burnup model underestimates the total 135Xe activity about 6.61% in the system, and the total activity of krypton and xenon in the system is underestimated by about 1.46%.Under the maximum removal fraction, the total activity of krypton and xenon in the exhaust gas system is 1.84×1016Bq, of which 83mKr, 85mKr, 87Kr, 88Kr, 133Xe, 135Xe and 138Xe account for about 95.6%.The total activity of krypton and xenon in the primary loop system is 2.64×1014Bq, of which 138Xe, 135mXe, 134mXe, 87Kr and 83mKr account for about 93.6%.The numerical simulation method and the conclusion consistent with the actual physical laws.Dynamic distribution, evolution and migration characteristics of krypton, xenon and these precursor in the primary loop in the molten salt can be simulated more accurately compared to static burnup model.The analysis results can provide a theoretical basis for the management scheme of airborne source termsthe cooling design of the radioactive exhaust system and the source term analysis in accident conditions for the molten salt reactor.

Fission product transport and capture in a molten salt reactor off-gas system

2020 ◽  
Author(s):  
Samuel Bryan ◽  
Heather Felmy ◽  
James Jerden ◽  
Hunter Andrews ◽  
Brian Riley ◽  
...  
Keyword(s):  
Fission Product ◽  
Molten Salt ◽  
Molten Salt Reactor ◽  
Gas System

scholarly journals Modeling Molten Salt Reactor Fission Product Removal with SCALE

2020 ◽  
Author(s):  
Pedro Jr vicente valdez ◽  
Benjamin R. Betzler ◽  
William Wieselquist ◽  
Massimilliano Fratoni
Keyword(s):  
Fission Product ◽  
Molten Salt ◽  
Molten Salt Reactor ◽  
Product Removal
Sign in / Sign up

Export Citation Format

Share Document