Published 2015 | Version v1
Book

Numerical prediction of deterioration in heat transfer in vertical supercritical water channels

  • 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)

Part of:
Proceedings of the international workshops on NPPs-safety and sustainability and new horizons in nuclear reactor thermal-hydraulics and safety

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.