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Flow and pressure profiles for the primary heat transport system of Rajasthan Atomic Power Station for the operation with few isolated reactor channels near the end shield cracks

Conference:

Abstract

The RAPS (Rajasthan Atomic Power Station) unit-1 is now operating at reduced power due to the removal of fifteen fuel channels for repair of south end shield cracks. The power level is restricted to 50% of the full power capacity as a precautionary measure. The relative difference that operation at 50% power and higher power would make to the end shield structure is being currently analysed with a view to operate this reactor at higher power levels. As a prerequisite, a detailed thermal hydraulic analysis is essential to assess the effect of reactor operation with isolated channels on the primary heat transport (PHT) system pressure, flow, temperature. The adequacy of the existing trip set points for the plant operation under this mode is also required to be assessed. In the present study, analysis of the PHT system has been carried out to determine the flow and pressure profiles for the RAPS heat transport system for operation of the reactor with isolated channels. (author). 5 refs., 1 fig., 1 tab.
Authors:
Gaikwad, A J; Chaki, S K; Sehgal, R L; Venkat Raj, V [1] 
  1. Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai (India)
Publication Date:
Jun 01, 1994
Product Type:
Conference
Report Number:
CONF-9406439-
Reference Number:
SCA: 210400; PA: AIX-29:018144; EDB-98:048927; SN: 98001952202
Resource Relation:
Conference: ACE-94: advances in chemical engineering in nuclear and process industries, Mumbai (India), 9-11 Jun 1994; Other Information: DN: 5 refs., 1 fig., 1 tab.; PBD: Jun 1994; Related Information: Is Part Of Advances in chemical engineering in nuclear and process industries; PB: 628 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FLOW RATE; HEAT TRANSFER; HYDRAULICS; PRESSURE GRADIENTS; PRIMARY COOLANT CIRCUITS; RAJASTHAN-1 REACTOR; REACTOR CHANNELS; REACTOR LATTICES; REACTOR OPERATION; SCRAM; THERMAL ANALYSIS; VALIDATION
OSTI ID:
591979
Research Organizations:
Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India).
Country of Origin:
India
Language:
English
Other Identifying Numbers:
TRN: IN9800257018144
Submitting Site:
INIS
Size:
pp. 100-104
Announcement Date:
Jan 23, 2004

Conference:

Citation Formats

Gaikwad, A J, Chaki, S K, Sehgal, R L, and Venkat Raj, V. Flow and pressure profiles for the primary heat transport system of Rajasthan Atomic Power Station for the operation with few isolated reactor channels near the end shield cracks. India: N. p., 1994. Web.
Gaikwad, A J, Chaki, S K, Sehgal, R L, & Venkat Raj, V. Flow and pressure profiles for the primary heat transport system of Rajasthan Atomic Power Station for the operation with few isolated reactor channels near the end shield cracks. India.
Gaikwad, A J, Chaki, S K, Sehgal, R L, and Venkat Raj, V. 1994. "Flow and pressure profiles for the primary heat transport system of Rajasthan Atomic Power Station for the operation with few isolated reactor channels near the end shield cracks." India.
@misc{etde_591979,
title = {Flow and pressure profiles for the primary heat transport system of Rajasthan Atomic Power Station for the operation with few isolated reactor channels near the end shield cracks}
author = {Gaikwad, A J, Chaki, S K, Sehgal, R L, and Venkat Raj, V}
abstractNote = {The RAPS (Rajasthan Atomic Power Station) unit-1 is now operating at reduced power due to the removal of fifteen fuel channels for repair of south end shield cracks. The power level is restricted to 50% of the full power capacity as a precautionary measure. The relative difference that operation at 50% power and higher power would make to the end shield structure is being currently analysed with a view to operate this reactor at higher power levels. As a prerequisite, a detailed thermal hydraulic analysis is essential to assess the effect of reactor operation with isolated channels on the primary heat transport (PHT) system pressure, flow, temperature. The adequacy of the existing trip set points for the plant operation under this mode is also required to be assessed. In the present study, analysis of the PHT system has been carried out to determine the flow and pressure profiles for the RAPS heat transport system for operation of the reactor with isolated channels. (author). 5 refs., 1 fig., 1 tab.}
place = {India}
year = {1994}
month = {Jun}
}