On the MTRR-SCW Concept of Nuclear Safety.
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| Title: | On the MTRR-SCW Concept of Nuclear Safety. |
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| 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] |
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| Database: | Engineering Source |
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| 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] |
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| ISSN: | 10637788 |
| DOI: | 10.1134/S1063778824100272 |
