Analysis of CSNI benchmark test on containment using the code CONTRAN
SK Haware, AK Ghosh, VV Raj, A Kakodkar - 1994 - osti.gov
A programme of experimental as well as analytical studies on the behaviour of nuclear
reactor containment is being actively pursued. A large number olexperiments on pressure …
reactor containment is being actively pursued. A large number olexperiments on pressure …
Development of a Multi-Compartment Containment thermal hydraulic code: PARIRODHAN
D Mittal, OS Gokhale, M Kumar - Nuclear Engineering and Design, 2022 - Elsevier
The development of a multi-compartment containment thermal–hydraulic code (named
PARIRODHAN) is presented in this paper. It provides the capability to predict the …
PARIRODHAN) is presented in this paper. It provides the capability to predict the …
Analysis of the CSF model for simulated loss of coolant accident conditions
An experimental facility called Containment Studies Facility (CSF) has been constructed at
the Bhabha Atomic Research Centre (BARC) for the purpose of research and development …
the Bhabha Atomic Research Centre (BARC) for the purpose of research and development …
[PDF][PDF] Effect of suppression pool swell on containment pressure transients during LOCA
VV I Thangamani, RK Singh, AK Ghosh - 2011 - repository.lib.ncsu.edu
In suppression pool type containments, the dry well (V1 Volume) and wet well (V2 Volume)
are connected through suppression pool via vent pipes. In case of LOCA, the steam flashes …
are connected through suppression pool via vent pipes. In case of LOCA, the steam flashes …
Preliminary evaluation of effect of Engineered Safety Features on source term for AHWR containment
Abstract The proposed Advanced Heavy Water Reactor (AHWR) employs double
containment envelope along with many Engineered Safety Features (ESFs) to mitigate the …
containment envelope along with many Engineered Safety Features (ESFs) to mitigate the …
[PDF][PDF] Vapour Suppression System (Pool Type) for Pressurised Heavy Water Reactor
AER Board - 2000 - aerb.gov.in
1.2 Objective This Safety Guide is intended to supplement the Code of Practice on Design
for Safety in Pressurised Heavy Water Based Nuclear Power Plants [1]. The main objective …
for Safety in Pressurised Heavy Water Based Nuclear Power Plants [1]. The main objective …
Hydrodynamics of AHWR Gravity-Driven Water Pool Under Simulated LOCA Conditions
I Thangamani, SM Ali, V Verma - Thorium—Energy for the Future: Select …, 2019 - Springer
The advanced heavy water reactor (AHWR) employs a double containment concept with a
large inventory of water within the gravity-driven water pool (GDWP) located at a higher …
large inventory of water within the gravity-driven water pool (GDWP) located at a higher …
Pretest analysis of containment studies facility model for simulated loss of coolant accident conditions
An experimental facility called Containment Studies Facility (CSF) has been constructed at
Bhabha Atomic Research Centre (BARC), Trombay for the purpose of research and …
Bhabha Atomic Research Centre (BARC), Trombay for the purpose of research and …
[PDF][PDF] Impact of Engineered Safety Features on AHWR Containment
I Thangamani, V Verma, RK Singh, AK Ghosh - 2009 - repository.lib.ncsu.edu
The proposed AHWR employs double containment envelope along with many Engineered
Safety Features (ESFs) to mitigate the consequences of LOCA with safety system failure …
Safety Features (ESFs) to mitigate the consequences of LOCA with safety system failure …
[PDF][PDF] Pretest analysis of CSF model for simulated loss of coolant accident conditions
I Thangamani, V Verma, RK Singh, AK Ghosh - 2009 - repository.lib.ncsu.edu
An experimental facility called Containment Studies Facility (CSF) has been constructed at
Bhabha Atomic Research Centre (BARC) for research and development in nuclear reactor …
Bhabha Atomic Research Centre (BARC) for research and development in nuclear reactor …