Variegated operation of MAPS reactors after enmasse' coolant channel replacement: a tale-tell signature of high standard fuel bundle production quality
Creators
- 1. Reactor Physics Section, Madras Atomic Power Station, Kalpakkam (India)
Description
After the Enmasse' Coolant Channel Replacement (EMCCR) of both the reactors of Madras Atomic Power Station (MAPS), they have put up a good performance, as far as core integrity is considered. This is a tale-tell signature of the high quality of the fuel bundles manufactured by Nuclear Fuel Complex (NFC), Hyderabad. Both the reactor cores have been loaded with various types of fuel bundles viz. Natural Uranium (NU), Depleted Uranium (DU), and Deeply Depleted Uranium (DDU) and were operated at different power level with different flux configuration at different stages of operation. Even around 1026 low burn up bundle (<2500 MWD/TeU) were transferred from MAPS-1 to MAPS-2, first time in the history of PHWRS. During all such variegated operations, the Primary Heat Transport (PHT) system 131I activity, which is synonymous with the core integrity, was maintaining low for most of the reactor operation period. However, recently a low burn up fuel bundle failure has been observed in MAPS-1. Even though the overall failure rate is very low, the cause of such failure needs to be ascertained for taking appropriate action to maintain the high standards of quality in the manufacturing process of the fuel bundles. (author)
Additional details
Publishing Information
- Publisher
- Nuclear Fuel Complex
- Imprint Place
- Hyderabad (India)
- Imprint Title
- Proceedings of the third international conference on characterization and quality control of nuclear fuels
- Imprint Pagination
- 186 p.
- Journal Page Range
- 1 p.
Conference
- Title
- 3. international conference on characterization and quality control of nuclear fuels
- Acronym
- CQCNF-2009
- Dates
- 18-20 Feb 2009
- Place
- Hyderabad (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 47115969
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILURE MODE ANALYSIS; FUEL ELEMENT CLUSTERS; KALPAKKAM-1 REACTOR; KALPAKKAM-2 REACTOR; NUCLEAR FUELS; PRIMARY COOLANT CIRCUITS; REACTOR CORES; URANIUM
- Descriptors DEC
- ACTINIDES; COOLING SYSTEMS; ELEMENTS; ENERGY SOURCES; ENERGY SYSTEMS; FUEL ASSEMBLIES; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS; METALS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR MATERIALS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS