On the MTRR-SCW Concept of Nuclear Safety.
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| Title: | On the MTRR-SCW Concept of Nuclear Safety. |
|---|---|
| Authors: | Lapin, A. S.1 (AUTHOR) Lapin_AS@nrcki.ru, Blandinsky, V. Yu.1 (AUTHOR) Blandinskiy_VY@nrcki.ru, Nevinitsa, V. A.1 (AUTHOR) Neviniza_VA@nrcki.ru, Fomichenko, P. A.1 (AUTHOR) Fomichenko_PA@nrcki.ru, Volkov, Yu. N.1 (AUTHOR) YNVolkov@mephi.ru |
| Source: | Physics of Atomic Nuclei. Dec2024, Vol. 87 Issue 10, p1394-1403. 10p. |
| Subjects: | Water cooled reactors, Control elements (Nuclear reactors), Light water reactors, Fast reactors, Nuclear reactor cores |
| Abstract: | The MTRR-SCW reactor is a light water cooled research reactor with a fast neutron spectrum in the nominal operation mode. None of the reactors in operation or under design have a combination of these features; therefore, special attention should be paid to the design of control rods and their location. The article considers various designs of control rods typical for the currently developed VVER-SCP power reactor, as well as for operating research reactors with a liquid-metal coolant and a fast neutron spectrum taking into account the MTRR-SCW features: a seven-element control rod assembly design and an annular absorber. For each of the considered designs, efficiency calculations are performed, and it is determined that the design of the control rod with an annular absorber has the highest specific efficiency. This design is chosen as the main one for the MTRR-SCW reactor. Criteria are proposed and optimization is carried out of the placement of control rods in the reactor core in order to reduce the uncertainty in obtaining neutron-physical characteristics in the central autonomous loop channel and to increase the flux density in it. When optimizing the placement of control rods in the research reactor, their influence on the main neutron-physical characteristics, and especially on their distribution during operation under nominal conditions, is taken into account. The emergency protection and compensating rods that compensate for temperature and density effects when the reactor reaches the nominal power level are removed; therefore, their influence on the neutron-physical characteristics of the reactor and the loop channel during operation is not significant, while the compensating rods are in the core and are removed as the fuel is burned out; therefore, their influence on the spatial distribution of neutron-physical characteristics will be significant. To reduce this influence, the burnup compensators and automatic control rods are proposed to be placed outside the core in the reflector. For different states of the reactor, the efficiency of efficiency of the control and protection system is evaluated. It is shown that in different states the control rods transfer the reactor to the required level of subcriticality in accordance with NP-009-17. [ABSTRACT FROM AUTHOR] |
| Copyright of Physics of Atomic Nuclei is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.) | |
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| Header | DbId: egs DbLabel: Engineering Source An: 183130443 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: On the MTRR-SCW Concept of Nuclear Safety. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Lapin%2C+A%2E+S%2E%22">Lapin, A. S.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> Lapin_AS@nrcki.ru</i><br /><searchLink fieldCode="AR" term="%22Blandinsky%2C+V%2E+Yu%2E%22">Blandinsky, V. Yu.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> Blandinskiy_VY@nrcki.ru</i><br /><searchLink fieldCode="AR" term="%22Nevinitsa%2C+V%2E+A%2E%22">Nevinitsa, V. A.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> Neviniza_VA@nrcki.ru</i><br /><searchLink fieldCode="AR" term="%22Fomichenko%2C+P%2E+A%2E%22">Fomichenko, P. A.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> Fomichenko_PA@nrcki.ru</i><br /><searchLink fieldCode="AR" term="%22Volkov%2C+Yu%2E+N%2E%22">Volkov, Yu. N.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> YNVolkov@mephi.ru</i> – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Physics+of+Atomic+Nuclei%22">Physics of Atomic Nuclei</searchLink>. Dec2024, Vol. 87 Issue 10, p1394-1403. 10p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Water+cooled+reactors%22">Water cooled reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Control+elements+%28Nuclear+reactors%29%22">Control elements (Nuclear reactors)</searchLink><br /><searchLink fieldCode="DE" term="%22Light+water+reactors%22">Light water reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Fast+reactors%22">Fast reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+reactor+cores%22">Nuclear reactor cores</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: The MTRR-SCW reactor is a light water cooled research reactor with a fast neutron spectrum in the nominal operation mode. None of the reactors in operation or under design have a combination of these features; therefore, special attention should be paid to the design of control rods and their location. The article considers various designs of control rods typical for the currently developed VVER-SCP power reactor, as well as for operating research reactors with a liquid-metal coolant and a fast neutron spectrum taking into account the MTRR-SCW features: a seven-element control rod assembly design and an annular absorber. For each of the considered designs, efficiency calculations are performed, and it is determined that the design of the control rod with an annular absorber has the highest specific efficiency. This design is chosen as the main one for the MTRR-SCW reactor. Criteria are proposed and optimization is carried out of the placement of control rods in the reactor core in order to reduce the uncertainty in obtaining neutron-physical characteristics in the central autonomous loop channel and to increase the flux density in it. When optimizing the placement of control rods in the research reactor, their influence on the main neutron-physical characteristics, and especially on their distribution during operation under nominal conditions, is taken into account. The emergency protection and compensating rods that compensate for temperature and density effects when the reactor reaches the nominal power level are removed; therefore, their influence on the neutron-physical characteristics of the reactor and the loop channel during operation is not significant, while the compensating rods are in the core and are removed as the fuel is burned out; therefore, their influence on the spatial distribution of neutron-physical characteristics will be significant. To reduce this influence, the burnup compensators and automatic control rods are proposed to be placed outside the core in the reflector. For different states of the reactor, the efficiency of efficiency of the control and protection system is evaluated. It is shown that in different states the control rods transfer the reactor to the required level of subcriticality in accordance with NP-009-17. [ABSTRACT FROM AUTHOR] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Physics of Atomic Nuclei is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.) |
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| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1134/S1063778824100272 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 10 StartPage: 1394 Subjects: – SubjectFull: Water cooled reactors Type: general – SubjectFull: Control elements (Nuclear reactors) Type: general – SubjectFull: Light water reactors Type: general – SubjectFull: Fast reactors Type: general – SubjectFull: Nuclear reactor cores Type: general Titles: – TitleFull: On the MTRR-SCW Concept of Nuclear Safety. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Lapin, A. S. – PersonEntity: Name: NameFull: Blandinsky, V. Yu. – PersonEntity: Name: NameFull: Nevinitsa, V. A. – PersonEntity: Name: NameFull: Fomichenko, P. A. – PersonEntity: Name: NameFull: Volkov, Yu. N. IsPartOfRelationships: – BibEntity: Dates: – D: 25 M: 12 Text: Dec2024 Type: published Y: 2024 Identifiers: – Type: issn-print Value: 10637788 Numbering: – Type: volume Value: 87 – Type: issue Value: 10 Titles: – TitleFull: Physics of Atomic Nuclei Type: main |
| ResultId | 1 |
