Abstract
The LR-0 research reactor operated by the Nuclear Research Institute in Rez is described. Particular attention is devoted to the reactor design. Described are the main and auxiliary moderator circuits and reactor control and protection systems, especially the control equipment, means to identify the reactor status, means for information processing and contact with the operators, means for controlling the neutron flux density, feed system, and experimental equipment. The dosimetric protection of the workplace is also dealt with. The design of the reactor core, of the technological circuits and control equipment makes it possible to perform physical experiments on WWER-1000 type cores over a wide region of numbers of assemblies, various degrees of fuel enrichment, arrangements of clusters in the reactor core, boric acid concentrations in moderator, etc. Physical measurements on light-water lattices of the WWER-440 type, studies of physical problems of shielding, investigation into spent fuel problems, and addressing nuclear safety problems are also possible. (J.B.). 7 figs., 3 refs.
Matejka, K;
[1]
Fleischhans, J;
Hejzlar, R
[2]
- ed.
- Ceske Vysoke Uceni Technicke, Prague (Czech Republic). Fakulta Jaderna a Fysikalne Inzenyrska; and others
Citation Formats
Matejka, K, Fleischhans, J, and Hejzlar, R.
Vol. 4: Technical descriptions of Czechoslovak research reactors. Part 2. Technical description of the LR-0 reactor; Sesit c. 4: Technicke popisy cs. vyzkumnych reaktoru: 2. dil - Technicky popis reaktoru LR-0.
Czech Republic: N. p.,
1994.
Web.
Matejka, K, Fleischhans, J, & Hejzlar, R.
Vol. 4: Technical descriptions of Czechoslovak research reactors. Part 2. Technical description of the LR-0 reactor; Sesit c. 4: Technicke popisy cs. vyzkumnych reaktoru: 2. dil - Technicky popis reaktoru LR-0.
Czech Republic.
Matejka, K, Fleischhans, J, and Hejzlar, R.
1994.
"Vol. 4: Technical descriptions of Czechoslovak research reactors. Part 2. Technical description of the LR-0 reactor; Sesit c. 4: Technicke popisy cs. vyzkumnych reaktoru: 2. dil - Technicky popis reaktoru LR-0."
Czech Republic.
@misc{etde_10122660,
title = {Vol. 4: Technical descriptions of Czechoslovak research reactors. Part 2. Technical description of the LR-0 reactor; Sesit c. 4: Technicke popisy cs. vyzkumnych reaktoru: 2. dil - Technicky popis reaktoru LR-0}
author = {Matejka, K, Fleischhans, J, and Hejzlar, R}
abstractNote = {The LR-0 research reactor operated by the Nuclear Research Institute in Rez is described. Particular attention is devoted to the reactor design. Described are the main and auxiliary moderator circuits and reactor control and protection systems, especially the control equipment, means to identify the reactor status, means for information processing and contact with the operators, means for controlling the neutron flux density, feed system, and experimental equipment. The dosimetric protection of the workplace is also dealt with. The design of the reactor core, of the technological circuits and control equipment makes it possible to perform physical experiments on WWER-1000 type cores over a wide region of numbers of assemblies, various degrees of fuel enrichment, arrangements of clusters in the reactor core, boric acid concentrations in moderator, etc. Physical measurements on light-water lattices of the WWER-440 type, studies of physical problems of shielding, investigation into spent fuel problems, and addressing nuclear safety problems are also possible. (J.B.). 7 figs., 3 refs.}
place = {Czech Republic}
year = {1994}
month = {Jun}
}
title = {Vol. 4: Technical descriptions of Czechoslovak research reactors. Part 2. Technical description of the LR-0 reactor; Sesit c. 4: Technicke popisy cs. vyzkumnych reaktoru: 2. dil - Technicky popis reaktoru LR-0}
author = {Matejka, K, Fleischhans, J, and Hejzlar, R}
abstractNote = {The LR-0 research reactor operated by the Nuclear Research Institute in Rez is described. Particular attention is devoted to the reactor design. Described are the main and auxiliary moderator circuits and reactor control and protection systems, especially the control equipment, means to identify the reactor status, means for information processing and contact with the operators, means for controlling the neutron flux density, feed system, and experimental equipment. The dosimetric protection of the workplace is also dealt with. The design of the reactor core, of the technological circuits and control equipment makes it possible to perform physical experiments on WWER-1000 type cores over a wide region of numbers of assemblies, various degrees of fuel enrichment, arrangements of clusters in the reactor core, boric acid concentrations in moderator, etc. Physical measurements on light-water lattices of the WWER-440 type, studies of physical problems of shielding, investigation into spent fuel problems, and addressing nuclear safety problems are also possible. (J.B.). 7 figs., 3 refs.}
place = {Czech Republic}
year = {1994}
month = {Jun}
}