Upflow conversion - Eliminating the potential for baffle jetting at McGuire
- 1. Duke Power Co., Huntersville, NC (United States)
- 2. Duke Power Co., Charlotte, NC (United States)
Description
Fuel failures indicative of baffle jetting were observed at Duke Power Company's McGuire units 1 and 2 in 1986 and 1987, respectively. In September 1990 the lower rector internals of unit 2 were modified to permanently eliminate the potential for baffle jetting. The unit 1 internals are to be converted in 1991. McGuire nuclear station is a two-unit, four-loop, Westinghouse pressurized water reactor with 17 by 17 fuel and a gross electrical output of 1,130 MW (electric) per unit. The modification performed on the unit 2 reactor internals resulted in a reversal in the direction of flow through the core barrel and baffle region. This flow reversal reduces the pressure drop across the baffle plates, thus eliminating the driving force for the baffle jets. This modification consists of plugging existing holes in the core barrel and opening new holes in the top former plate to change the flow direction
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 400-401
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 2-6 Jun 1991.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23040042
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BAFFLES; FLUID FLOW; FUEL ELEMENT FAILURE; HYDRAULICS; INSPECTION; JETS; MC GUIRE-1 REACTOR; MC GUIRE-2 REACTOR; MODIFICATIONS; PRESSURE VESSELS; RADIATION DOSES; RADIATION PROTECTION; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR CORES; REACTOR OPERATION; REMOTE VIEWING EQUIPMENT
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910603--.