Improvements in the reactor core isolation cooling (RCIC) pump model
Creators
- 1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Description
As part of the efforts to understand the unexpected "self-regulating" mode of the RCIC (Reactor Core Isolation Cooling) systems that was observed during the Fukushima accidents and to extend BWR RCIC and PWR AFW (Auxiliary Feed Water) operational range and flexibility, mechanistic models for the Terry turbine are being developed and tested with the RELAP-7 code to simulate the RCIC system. In the previous work, we developed a set of analytical models for the normal working conditions, as well as the two-phase off-design conditions, of the RCIC system, based on Sandia's original work. An under-expanded jet model was developed to replace the CFD-based reduced-order model in the Sandia work to obtain the velocity and thermodynamic conditions of the turbine stator inlet. The models include both an adiabatic expansion process inside the nozzle and a free expansion process outside of the nozzle to ambient pressure. For the two-phase off-design conditions, two well-established choking models were used - the Isentropic Homogenous Equilibrium Model (IHEM) and Moody's model. The new twophase Terry turbine model used the choking models to calculate the mass flow rate, the critical pressure at the nozzle throat, and steam quality. The two-phase nozzle expansion model was also developed by considering the vapor phase with a similar model for the single-phase case with the assumption that the liquid phase would slip along the wall with a much slower speed and will not contribute to the impulse on the rotor.
Availability note (English)
Available from https://inldigitallibrary.inl.gov/sites/sti/sti/Sort_4725.pdf; PURL: http://www.osti.gov/servlets/purl/1467421/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 29 p.
- Report number
- INL/EXT--18-44739-Rev000
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 50053766
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CRITICAL PRESSURE; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; PWR TYPE REACTORS; RCIC SYSTEMS; REACTOR ACCIDENTS; REACTOR CORES; TURBINES
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; MACHINERY; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SITES; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TURBOMACHINERY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE (United States)
- Secondary number(s)
- OSTIID--1467421