Numerical prediction of deterioration in heat transfer in vertical supercritical water channels
Creators
- 1. Discipline of Mechanical Engineering, PDPM Indian Institute of Information Technology, Design and Manufacturing, Jabalpur (India)
Description
The present work investigates the numerical prediction capabilities of the thermal-hydraulic model, THRUST for predicting the event of deterioration in heat transfer in a vertical supercritical channel under high mass flow rates. Available experimental data is taken as the basis of the present investigation where DHTC was observed for a range of bulk enthalpies under supercritical pressure flow conditions. The simulation begins with the steady state numerical analysis of the same experiment in order to validate the results obtained against that of the experimental ones. The deterioration in heat transfer predicted used the different heat transfer coefficient correlations in order to predict the required wall temperature values and their capability in predicting the deterioration is compared. This steady state simulation is then followed by a numerical simulation of the fast transient case study following a time dependent depressurization of the channels. The transient responses following the perturbation are obtained until the new asymptotic steady state is achieved. It has been observed that the predicted values of the wall temperatures in the case of time dependent depressurization of the channel leads to a much severe DHT being observed as compared to that of the steady state result. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Regulatory Board
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the international workshops on NPPs-safety and sustainability and new horizons in nuclear reactor thermal-hydraulics and safety
- Imprint Pagination
- 769 p.
- Journal Page Range
- 7 p.
Conference
- Title
- international workshop on NPPs-safety and sustainability; NHNRTHS-2015: international workshop on new horizons in nuclear reactor thermal-hydraulics and safety
- Acronym
- CANSAS-2015
- Dates
- 8-11 Dec 2015
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 48073050
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; REACTOR COOLING SYSTEMS; REACTOR SAFETY; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; TURBULENT FLOW
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR COMPONENTS; SAFETY
Optional Information
- Notes
- 14 refs., 6 figs., 1 tab.