Korean experience in CANDU-PHWR operation
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6263825
Among KEPCO's 9 nuclear power units, Korea Nuclear Unit No. 3, the Wolsung Nuclear Power Plant is the only CANDU-PHWR Unit, while the rest of 8 others are PWR units. The unit was designed by Atomic Energy of Canada, Ltd. of Canada, who also performed overall project management for the plant construction under the provisions and arrangement of the relevant contracts. The gross electrical output of the plant is 678.7 MWe and thermal output of the reactor is 2061 MWth. While these figures lead to lower plant efficiency than LWR counterparts, unit energy cost for fuel is more favorable than LWRs because natural uranium is utilized for the fuel bundles, some of which are already being fabricated domestically. Annual capacity factors for 1983 and 1984 could have been improved, if two major planned outages for the modification works on steam generator internals and one major forced outage from the heavy water spill incident could be eliminated. The heavy water spill incident in November, 1984 brought plant staffs many lessons to learn and many things to contemplate. Unique design concepts and features such as on-power refuelling, poison prevent mode, versatile plant control system built around digital computers and power step back/set back logics may be credited for these relatively good plant performances. Human related factors such as staff's technical capabilities and strong will toward good performance were other elements which could not be overlooked.
- Research Organization:
- Korea Electric Power Corporation, Seoul
- OSTI ID:
- 6263825
- Report Number(s):
- CONF-870905-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 56:1
- Country of Publication:
- United States
- Language:
- English
Similar Records
Development of PHWR fuel fabrication in Korea
SOPHT: a computer model for CANDU-PHWR heat transport works and their control
How the CANDU 600 meets the ALARA principle
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6171982
SOPHT: a computer model for CANDU-PHWR heat transport works and their control
Journal Article
·
Sat Oct 01 00:00:00 EDT 1977
· Nucl. Technol.; (United States)
·
OSTI ID:7279306
How the CANDU 600 meets the ALARA principle
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6342216
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
ASIA
BOILERS
CANDU TYPE REACTORS
CONSTRUCTION
CONTROL SYSTEMS
DEVELOPING COUNTRIES
FUEL ELEMENTS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
HUMAN FACTORS
NATURAL URANIUM REACTORS
NUCLEAR POWER
OPERATION
PERFORMANCE
PHWR TYPE REACTORS
POWER
POWER GENERATION
POWER REACTORS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
REPUBLIC OF KOREA
SAFETY
STEAM GENERATORS
THERMAL REACTORS
VAPOR GENERATORS
WOLSUNG-1 REACTOR
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
ASIA
BOILERS
CANDU TYPE REACTORS
CONSTRUCTION
CONTROL SYSTEMS
DEVELOPING COUNTRIES
FUEL ELEMENTS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
HUMAN FACTORS
NATURAL URANIUM REACTORS
NUCLEAR POWER
OPERATION
PERFORMANCE
PHWR TYPE REACTORS
POWER
POWER GENERATION
POWER REACTORS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
REPUBLIC OF KOREA
SAFETY
STEAM GENERATORS
THERMAL REACTORS
VAPOR GENERATORS
WOLSUNG-1 REACTOR