Liquid-salt channel-type reactor with dynamic loading and core superposition

Котов, В. М.; Котов, С. В.; Takibaev, Zh.S.; Tikhomirov, L. N.

doi:10.1080/10519990500186510

Cited by 5 publications

(5 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Work [10] shows that this regime can significantly simplify a molted salt reactor technology of fuel purification from fission products and actinides.…”

Section: Dynamic Loading Regime Usementioning

confidence: 99%

Thermal Reactors with High Reproduction of Fission Materials

Котов¹

2012

Nuclear Power- Practical Aspects

View full text Add to dashboard Cite

“…Work [10] shows that this regime can significantly simplify a molted salt reactor technology of fuel purification from fission products and actinides.…”

Section: Dynamic Loading Regime Usementioning

confidence: 99%

Thermal Reactors with High Reproduction of Fission Materials

Котов¹

2012

Nuclear Power- Practical Aspects

View full text Add to dashboard Cite

“…Less absorption in long-lived fission products is possible with use of interim fuel cleaning in campaign from accumulated fission products. This cleaning is foreseen for liquid salt reactors, but large effect of it is also possible in solid fuel reactors [6].…”

Section: Losses Decreasingmentioning

confidence: 99%

“…), were researched [5]. This technology decreases neutron losses in 135 Xe due to its decay during sustaining and can be easily applied in liquid salt reactors with additional simplification of fuel reprocessing [6].…”

Section: Introductionmentioning

confidence: 99%

Thermal Energetic Reactor with High Reproduction of Fission Materials

Котов

2012

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

Existing thermal reactors are energy production scale limited because of low portion of raw uranium usage. Fast reactors are limited by reprocessing need of huge mass of raw uranium at the initial stage of development. The possibility of development of thermal reactors with high fission materials reproduction, which solves the problem, is discussed here. Neutron losses are decreased, uranium-thorium fuel with artificial fission materials equilibrium regime is used, additional in-core and out-core neutron sources are used for supplying of high fission materials reproduction. Liquid salt reactors can use dynamic loading regime for this purpose. Preferable construction is channel type reactor with heavy water moderator. Good materials for fuel element shells and channel walls are zirconium alloys enriched by90Zr. Water cooled reactors with usage 12% of raw uranium and liquid metal cooled reactors with usage 25% of raw uranium are discussed. Reactors with additional neutron sources obtain full usage of raw uranium with small additional energy expenses. On the base of thermal reactors with high fission materials reproduction world atomic power engineering development supplying higher power and requiring smaller speed of raw uranium mining, than in the variant with fast reactors, is possible.

show abstract

“…A run in this case should be regarded as the operation of the reactor until the required fuel burnup with purification of the fuel is reached [6]. Using external sources of neutrons [7] to produce the initial 233 U to be added will make it possible to reach the maximum possible fuel burnup (Table 2). When the reactor begins operating, the composition of fissile materials can be limited by 235 U, whose amount in the fuel will be somewhat greater than the amount of fissile substances in an equilibrium regime and their low concentration in the fuel will make it possible to reach an equilibrium regime in a short period of time.…”

Section: Use Of 233 U Instead Of 235 Umentioning

confidence: 99%

Breeding of fissile materials in thermal reactors

Котов

2007

At Energy

Self Cite

View full text Add to dashboard Cite

It is predicted that by the end of the 21st century nuclear power plants with fast reactors will be able to meet no more than 30% of the electricity demand [1]. For thermal reactors with similar power, the proven reserves of cheap uranium will be consumed over approximately 50 years. Thermal reactors will be able to compete with fast reactors if they breed more fissile material. In this problem, preference is given to reactors that will burn fuel containing thorium. For example, a variant of an upgraded CANDU reactor where 233 U is produced completely is presented in [2].The breeding ratio for fissile materials in a thermal reactor can be made to approach 1 with a low concentration of fissile substances in the fuel, decreasing neutron losses in the structural materials and leakage. The following questions become important. Is it possible in this approach to reach high burnup? What will be the admissible neutron losses in materials and due to leakage? How realistic will the design be? What niche in power production will these reactors be able to fill?An acceptable result according to certain indicators can be achieved with the following solutions [3]:• the reactor operates according to a core superposition technology, where the excess neutrons present at the start of a run are used for breeding fissile materials at the end of the run, and the reactivity integrated over the campaign is close to zero; • the reactor operates in a closed fuel cycle with equilibrium chains of nuclides, whose parents are 232 Th and 238 U; • neutron losses are as low as possible, for which reactivity compensators are eliminated and structural materials enriched with isotopes with small neutron capture cross-sections are used; • an additional neutron source is present -the reaction n-2n. A variant of a reactor with the smallest possible dimensions is displayed in Fig. 1. Its core contains 475 technological channels. Figure 2 displays the geometry of a fuel assembly. The fuel elements cladding and the channel housing are made of zirconium-niobium alloy with up to 99% 99 Zr. This variant, according to the number of channels in the core and the core dimensions, is close to optimal for thermal power ranging from 600 to 1500 MW(t).The characteristics of the reactor were calculated in the following sequence. The construction of the reactor core and fuel assemblies was worked out. The MCNP program was used to calculate the neutron-physical characteristics and to determine, based on these characteristics, the neutron losses in the structural materials and due to leakage, and the cross-sections of nuclides for the single-group point model used for a reactor in the Dinamika program [4]. Next, the change in the composition of the fuel during a run and the neutron losses in fission products with prescribed run time were found. If the conditions for equilibrium of nuclides or zero reactivity integral were violated in the calculations, then a new series of calculations was conducted with new initial conditions. The reprocessing of the spent fuel from t...

show abstract

Liquid-salt channel-type reactor with dynamic loading and core superposition

Cited by 5 publications

References 0 publications

Thermal Reactors with High Reproduction of Fission Materials

Thermal Reactors with High Reproduction of Fission Materials

Thermal Energetic Reactor with High Reproduction of Fission Materials

Breeding of fissile materials in thermal reactors

Contact Info

Product

Resources

About