Testing the reactor charging machine
Creators
- 1. Institute for Nuclear Research - Pitesti, PO Box 78, RO-0300 Pitesti (Romania)
Description
One of the main objective of the R - D technological engineering program devoted to the Fuel Handling System is domestic production of equipment and technology for testing the ends of the reactor charging machine (MID) destined to Cernavoda NPP, beginning with Unit 2. To achieve the objective based on an own design, a bench-scale testing stand of MIDs which can simulate the pressure, flow-rate, and temperature conditions proper to fuel channels in operating CANDU 600 reactors. The main components of this testing facility are: - fuel channels, cold also test sections, allowing the coupling of MID end upwardly and downwardly, corresponding to the direction of the water flow through the channel; - technological installation feeding with light water the testing sections of the facility in thermohydraulic conditions, similar to those in the reactor, allowing the cold and hot testings, respectively, of the MID end; - cold testing installation, water supply and oil control panel, feeding the hydraulic drives of the MID's end during the testings; - fixed bridge and mobile carrier for MID's end positioning against testing sections; - installation for functional testing of MID thrusters, before pre-admission and reception tests; - dedicated tools and devices; - raising and transport mechanical devices for handling and positioning the MID's end upon the carrier; - automation panel for controlling the stand equipment and MID's end; - process computer for conducting on-line tests. MID's end testing implies mainly the following operations: - regulation, calibration and functional testing of the MID thrusters carried out independently on a specialised stand; - regulation and calibration of MID's end sub-assemblages; - carrying out the cold and hot pre-admission tests consisting in automatic performing, without operator intervention, of 12 fuel changes, two of which being successive; - performing the cold and hot reception tests, consisting in automatic accomplishment of 4 successive fuel changes, using as algorithm the modified plant code Job R6. The paper contains also an account of the current status of this project as well as a description of the results obtained so far and the last measures of revamping the installation
Availability note (English)
Available from author(s) or Institute for Nuclear Research - Pitesti, PO Box 78, RO-0300 Pitesti (RO). Fax 40-48-262449Additional details
Additional titles
- Original title (Romanian)
- Testarea masini de incarcat - descarcat combustibil
Publishing Information
- Publisher
- Institute for Nuclear Research - Pitesti
- Imprint Place
- Pitesti (Romania)
- Imprint Title
- Nuclear Power - Current Status and Perspectives. INR 1971-2001 Symposium. Volume II
- Imprint Pagination
- 304 p.
- Journal Page Range
- p. 57-58
Conference
- Title
- Nuclear Power - Current Status and Perspectives. INR 1971-2001 Symposium
- Original Conference Title
- Conferinta ENERGETICA NUCLEARA - PREZENT SI VIITOR. ICN 1971-2001. Volum II
- Dates
- 13 Jul 2001
- Place
- Pitesti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 32053735
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; CALIBRATION; CANDU TYPE REACTORS; CONTROL EQUIPMENT; HYDRAULIC CONTROL DEVICES; J CODES; MATERIALS HANDLING EQUIPMENT; NUCLEAR FUELS; PERFORMANCE; PERFORMANCE TESTING; REACTOR CHARGING MACHINES
- Descriptors DEC
- COMPUTER CODES; CONTROL EQUIPMENT; ENERGY SOURCES; EQUIPMENT; FUELS; HEAVY WATER MODERATED REACTORS; HYDRAULIC EQUIPMENT; MATERIALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; TESTING; THERMAL REACTORS
Optional Information
- Notes
- Imprint:Conferinta ENERGETICA NUCLEARA - PREZENT SI VIITOR. ICN 1971-2001. Volum II