ESBWR - Robust Design for Power Maneuvering and Load Following Effectiveness - 14404
Creators
- 1. GE-Hitachi Nuclear Energy, 3901 Castle Hayne Road, M/C A-70, Wilmington, North Carolina 28401 (United States)
Description
The ESBWR is a 4500 MWt Generation III+ natural circulation reactor design with an array of robust features and passive safety systems to deliver reliable electric output and keep the reactor safe during postulated transients and accidents. The ESBWR is nearing the completion of the US Nuclear Regulatory Commission design certification process and is being licensed for two US sites. This paper focuses on the maneuvering of the ESBWR plant through the expected states, power level, and plant modes during startup, shutdown and normal operation, and load following, as well as during surveillances done at power. Power maneuvering specification is needed as an input for plant configuration change, task analysis, and procedure development. This paper includes plant maneuvering in the core power-feedwater temperature operating domain, while remaining within stability boundaries. Plant maneuvering requirements are specified in the context of the following: a) the ESBWR Core Power and Feedwater Temperature Operating Domain; b) maneuvering with control rods and feedwater temperature change from cold xenon free shutdown conditions to rated power, and maneuvering during hot startup; c) maneuvering for the initial core and equilibrium core loading patterns; d) applicable power maneuvering (including load following) and plant availability related requirements; and e) a First-of-a-Kind test of power maneuvering to be conducted during the initial startup of the first ESBWR. Technical Specification Thermal Operating Limits and Soft Duty Guidelines are met and applicable industry guidelines have also been considered. Meeting the Soft Duty Guidelines provide assurance that fuel failure related radiological impact remains within the established limits and helps to meet the ALARA requirements. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-776-7
- Imprint Pagination
- 10 p.
Conference
- Title
- International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP 2014
- Dates
- 6-9 Apr 2014
- Place
- Charlotte, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54022702
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALARA; CERTIFICATION; CONFIGURATION; CONTROL ELEMENTS; LICENSES; NATURAL CONVECTION; NUCLEAR FUELS; REACTOR DESIGN; REACTOR SAFETY; REACTOR SHUTDOWN; RECOMMENDATIONS; SPECIFICATIONS; STEADY-STATE CONDITIONS; US NRC
- Descriptors DEC
- CONVECTION; DESIGN; ENERGY SOURCES; ENERGY TRANSFER; FUELS; HEAT TRANSFER; MASS TRANSFER; MATERIALS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; SAFETY; SHUTDOWN; US ORGANIZATIONS
Optional Information
- Notes
- 18 refs.; Available on CD-ROM from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)