The daily load follow capability of the Smart reactor core without the soluble boron change in the primary coolant
Creators
- Song, J. S.1
- Park, S. Y.1
- Kim, K. K.1
- Kim, H. R.1
- Instituto Nacional de Investigaciones Nucleares (ININ), Estado de Mexico (Mexico)
- International Atomic Energy Agency (IAEA), Vienna (Austria)
- Secretaria de Energia (SENER), Mexico D. F. (Mexico)
- Pacific Nuclear Council (PNC), Sidney (Australia)
- Sociedad Nuclear Mexicana (SNM), Mexico D. F. (Mexico)
- Nuclear Energy Agency (NEA), Paris (France)
- Academia de Ingenieria (AI), Mexico D. F. (Mexico)
- 1. Korea Atomic Energy Research Institute, 1045 Daedeok-daero Yuseong-Gu, 305-353 Daejeon (Korea, Republic of)
Description
Smart is an integral pressurized water reactor which has a pressurizer, 8 steam generators and 4 reactor coolant pumps on the inside of the reactor vessel. The thermal power of the core is 330 MW. The core has 57 17 x 17 rectangular fuel assemblies with a 200 cm effective height and the core reactivity is controlled by 25 control rod assemblies and the soluble boron in primary coolant. The core power control is based on the predetermined core outlet temperature with ± 1.5 C allowance so that the pressure change of the pressurizer is minimized for the power variation. The capability of the load follow operation is evaluated for a daily load follow scheme of 12-3-6-3, the power variation of which is from 100% to 50%. The evaluation is performed by 3-dimensional core simulations with the xenon transient calculation for the beginning and the end of cycles. Three major parameters axial offset, radial and three dimensional peaking factors related to operation limits are analyzed. It shows that all of those are varied, within limits with enough margins, without the change of the soluble boron in the primary coolant but with the automatic control rod movement only. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: javier.ortega@inin.gob.mx; claudio.fernandez@inin.gob.mxAdditional details
Publishing Information
- Publisher
- Mexican Nuclear Society
- Imprint Place
- Mexico, D. F. (Mexico)
- ISBN
- 978-607-95174-1-0
- Imprint Pagination
- 8 p.
Conference
- Title
- an environmentally sound option
- Acronym
- 21. Mexican Nuclear Society Meeting; 17. Pacific Basin Nuclear Conference. Nuclear energy
- Dates
- 24-30 Oct 2010
- Place
- Cancun, Q.R. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 42014586
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BORON; CONTROL; CONTROL ELEMENTS; COOLANTS; EVALUATION; FUEL ASSEMBLIES; HEIGHT; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTIVITY; REACTOR CORES; REACTOR OPERATION; REACTOR VESSELS; SIMULATION; STEAM GENERATORS; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; VARIATIONS; XENON
- Descriptors DEC
- BOILERS; CONTAINERS; COOLING SYSTEMS; DIMENSIONS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUIDS; GASES; NONMETALS; OPERATION; POWER REACTORS; RARE GASES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SEMIMETALS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Korea Atomic Industrial Forum, Inc. (Korea, Republic of); Mitsubishi Nuclear Energy Systems Inc. (United States); Westinghouse-Toshiba (United States); Hitachi, Ltd. (United States); Nukem (Germany); Iberdrola, Ingenieria y Construccion (Spain); NAC International (United States); Korea Atomic Energy Research Institute (Korea, Republic of); Grupo IAI (Mexico)