Two-Fluid Molten-Salt Breeder Reactor Design Study (Status as of January 1, 1968).

Robertson, R.C.; Briggs, R. B.; Smith, O.L.; Bettis, E.S.

doi:10.2172/4093364

Cited by 30 publications

(38 citation statements)

References 6 publications

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“…Liquid-molten-salt fuel was well studied along with the successful use of UF 4 -7 LiF-BeF 2 -ZrF 4 (65:29:5:1) at the Molten-Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory [5,6]. Considering these facts, we use the composition UF 4 -7 LiF-BeF 2 = 40:46:14 in the present study after adjustment to obtain criticality with an appropriate excess reactivity.…”

Section: Reactor System and Core Design Conceptmentioning

confidence: 99%

“…It is worth noting that the volume of the peripheral region is larger than the core center region for the same radial width yielding an importance to the periphery in the total thermal power. Though no fissile exists in the reflector as seen in Figure 8, the persistent increase of the third-group flux toward the inner periphery of the reflector leads to a large reactivity worth of the control material 6 Li in it as far as it is close to the fuel-reflector boundary as shown in Figure 10. The reactivity worth of the absorber is defined as k in − k out , where k in stands for the k eff with only one of the three LRMs inserted and k out for all the absorbers withdrawn.…”

Section: Neutron Flux Reaction Rate Distribution Andmentioning

confidence: 99%

“…When the core temperature rises high enough for LRM start-up, the LRM provides a positive reactivity (green in Figure 11(b) and (c)) by extracting the 6 Li absorber from the core region. We set this temperature to be 463 K, or the lithium melting temperature plus 10 K, taking into account the time lag of heat conduction from the core to the frozen seal, effectively (see Figure 2).…”

Section: Start-up Sequence In Orbitmentioning

confidence: 99%

“…As the core temperature continues to rise further, the LEM starts negative reactivity insertion. Specifically, the 6 Li absorber in the LEM reservoir starts melting and pouring into the core as a result of the thermal expansion (blue in Figure 11(c)). The 6 Li of the LEM melts at 456 K and the negative reactivity insertion starts at 1266 K by thermal expansion as shown in Figure 12.…”

Section: Start-up Sequence In Orbitmentioning

confidence: 99%

“…Specifically, the 6 Li absorber in the LEM reservoir starts melting and pouring into the core as a result of the thermal expansion (blue in Figure 11(c)). The 6 Li of the LEM melts at 456 K and the negative reactivity insertion starts at 1266 K by thermal expansion as shown in Figure 12. When the core achieves the nominal operation temperature, the LEM supplies the 6 Li absorber down not to the bottom but to the middle of the active core height.…”

Section: Start-up Sequence In Orbitmentioning

confidence: 99%

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Design study of molten-salt-type reactor for powering space probes and its automated start-up

Kimura

Yoshida

2013

Journal of Nuclear Science and Technology

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Space probes exploring the deep space need a noticeable amount of electricity for powering their instrumentation (5-8 kWe). The solar battery, however, is not able to afford this because of the extended distance between the probe and the sun. Furthermore, the radioisotope thermoelectric generator (RTG) may be extraordinarily sizable for this purpose. On the contrary, installation of nuclear reactor on the probes seems to be promising for the reasons such as its small mass, stability, and its high power density. Especially, the deep-space sample return mission has an essential demand for a nuclear reactor typically with the following specifications: 10-year reactor employment time, total system mass less than 500 kg, and electricity output more than 8 kWe. High power density is the key to realize these requirements. The thermal electricity conversion efficiency of a space reactor increases in accordance with the rise of the core temperature. Thus, in the present study, we propose a use of the molten-salt fuel considering that this type of fuel can achieve high core temperature over 1000 K. In addition to the space reactor for the space exploration, autonomic reactor control is extremely desirable because real-time control from the earth is difficult because of the long time lag of mutual communication. The molten-salt space reactor proposed in the present paper satisfies all the above essential demands primarily owing to the high-temperature operation availability. In addition, we concluded that the automatic reactor start-up in its orbit is feasible by virtue of introduction of novel reactivity-control devices proposed by Kambe (Kambe, Sato, Tsunoda.

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Section: Reactor System and Core Design Conceptmentioning

confidence: 99%

Section: Neutron Flux Reaction Rate Distribution Andmentioning

confidence: 99%

Section: Start-up Sequence In Orbitmentioning

confidence: 99%

Section: Start-up Sequence In Orbitmentioning

confidence: 99%

Section: Start-up Sequence In Orbitmentioning

confidence: 99%

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Design study of molten-salt-type reactor for powering space probes and its automated start-up

Kimura

Yoshida

2013

Journal of Nuclear Science and Technology

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References

2019

Nuclear Power

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Steady-state reactor physics of the dual fluid reactor concept

Wang

Macián‐Juan

2018

Int J Energy Res

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Summary The dual fluid reactor (DFR) is a molten salt fast reactor developed by the Institut fuer Festkoerper‐Kernphysik (Berlin) on the basis of the Gen‐IV molten salt reactor and liquid metal–cooled reactor (sodium‐cooled fast reactor and lead‐cooled fast reactor) concepts. In the concept, the fuel is selected with the molten chloride salt and the coolant is the liquid lead. The article establishes the model for the reactor physics analysis and summarizes the preliminary performed calculations and the achieved results so far by the author on the steady‐state reactor physics behavior with the default fuel salt of U‐Pu mixture under zero‐flow‐velocity conditions. They include criticality calculation, neutron spectrum, spatial flux distribution, reaction rates and power distribution, nuclide importance, and temperature coefficient. The conclusion of the article evaluates the reactor physics behavior of the DFR concept and gives comments on the concept itself as well as on the future researches. The article is modified from a part of the PhD thesis of the first author (X. Wang).

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Two-Fluid Molten-Salt Breeder Reactor Design Study (Status as of January 1, 1968).

Abstract: MASTER

Cited by 30 publications

References 6 publications

Design study of molten-salt-type reactor for powering space probes and its automated start-up

Design study of molten-salt-type reactor for powering space probes and its automated start-up

References

Steady-state reactor physics of the dual fluid reactor concept

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