Water level instrumentation simulation
- 1. Fauske and Associates, Inc., Burr Ridge, IL (United States)
Description
Through simulation, evaluations of system performance can be made to increase efficiency, reduce costs, enhance safety and provide effective training. A full function simulation for evaluating water level measurement requires modeling the physical process, the process instrumentation response and where appropriate, the human input/response. This paper examines a full function application simulating the primary system water level in a Boiling Water Reactor (BWR). The physical processes associated with BWR vessel level response are modeled with the Modular Accident Analysis Program (MAAP). The MAAP code is used as the basis for providing primary system and containment thermal-hydraulic response to a compendium of expected plant transients. The BWR vessel level instruments is modeled with the FAI developed Instrumentation PACkage (IPAC). With the thermal-hydraulic input from MAAP, the IPAC software models the various phenomena associated with water level measurements including the effects due to: (1) instrument channel calibration, (2) instrument drift and (3) containment (drywell) environmental effects. This paper discusses the IPAC models (instrumentation components) along with the factors which influence the mass balance of water in the downcomer region. A comparison of the BWR vessel water level complete simulation package to data from a simulated BWR plant transient culminates the discussion of this paper. The full function simulation package presented in this paper, enables a software-based representation of the BWR vessel level to be evaluated under various hypothetical plant conditions including normal, accident, and severe accident events. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-47-X
- Imprint Title
- Simulation methods in nuclear engineering
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.2) [13 p.]
Conference
- Title
- 5. International conference on simulation methods in nuclear engineering
- Dates
- 8-11 Sep 1996
- Place
- Montreal, PQ (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 33018571
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; HYDRAULIC CONDUCTIVITY; I CODES; NUCLEAR POWER PLANTS; ON-LINE MEASUREMENT SYSTEMS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; THERMAL CONDUCTIVITY
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; ON-LINE SYSTEMS; PHYSICAL PROPERTIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs., 1 tabs., 12 figs.