The present experimental investigation in a scaled facility of an Indian pressurized heavy water reactors (PHWRs) is focused on the heat transfer behavior from the calandria vessel (CV) to the calandria vault during a prolonged severe accident condition in the presence of decay heat. The transient heat transfer simulates the conditions from single phase to boiling in the calandria vault water, partial uncovery of the CV due to boil off of water in the vault, and refill of calandria vault. Molten borosilicate glass was used as the simulant due to its comparable heat transfer characteristics similar to prototypic material. About 60 kg of the molten material was poured into the test section at about 1100 °C. Decay heat in the melt pool was simulated by using high watt cartridge type heaters. The temperature distributions inside the molten pool across the CV wall thickness and vault water were measured for prolonged period which can be divided into various phases, viz., single phase natural convection heat transfer in calandria vault, boiling heat transfer in calandria vault, partial uncovery of CV, and refilling calandria vault. Experimental results showed that once the crust formed, the inner vessel temperature remained very low and vessel integrity maintained. Even boiling of calandria vault water and uncovery of CV had negligible effect on melt, CV, and vault water temperature. The heat transfer coefficients on outer vessel surface were obtained and compared with various conditions.
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July 2018
Research-Article
Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration
Sumit V. Prasad,
Sumit V. Prasad
Homi Bhabha National Institute,
Anushaktinagar,
Mumbai 400094, India;
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Mumbai 400085, India
e-mail: svprasad@barc.gov.in
Anushaktinagar,
Mumbai 400094, India;
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Mumbai 400085, India
e-mail: svprasad@barc.gov.in
Search for other works by this author on:
A. K. Nayak
A. K. Nayak
Homi Bhabha National Institute,
Anushaktinagar,
Mumbai 400094, India;
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Mumbai 400085, India
e-mail: arunths@bacr.gov.in
Anushaktinagar,
Mumbai 400094, India;
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Mumbai 400085, India
e-mail: arunths@bacr.gov.in
Search for other works by this author on:
Sumit V. Prasad
Homi Bhabha National Institute,
Anushaktinagar,
Mumbai 400094, India;
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Mumbai 400085, India
e-mail: svprasad@barc.gov.in
Anushaktinagar,
Mumbai 400094, India;
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Mumbai 400085, India
e-mail: svprasad@barc.gov.in
A. K. Nayak
Homi Bhabha National Institute,
Anushaktinagar,
Mumbai 400094, India;
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Mumbai 400085, India
e-mail: arunths@bacr.gov.in
Anushaktinagar,
Mumbai 400094, India;
Reactor Engineering Division,
Bhabha Atomic Research Centre,
Mumbai 400085, India
e-mail: arunths@bacr.gov.in
1Corresponding authors.
Manuscript received June 29, 2017; final manuscript received March 13, 2018; published online May 16, 2018. Assoc. Editor: Jovica R. Riznic.
ASME J of Nuclear Rad Sci. Jul 2018, 4(3): 031014 (11 pages)
Published Online: May 16, 2018
Article history
Received:
June 29, 2017
Revised:
March 13, 2018
Citation
Prasad, S. V., and Nayak, A. K. (May 16, 2018). "Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration." ASME. ASME J of Nuclear Rad Sci. July 2018; 4(3): 031014. https://doi.org/10.1115/1.4039636
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