Sodium-Free Level Fluctuations: Concern on Structural Integrity for the Pool-Type Sodium-Cooled Fast Breeder Reactor

2017 ◽  
pp. 407-417
Author(s):  
V. R. Chandan Reddy ◽  
R. Suresh Kumar ◽  
Anil Kumar Sharma ◽  
K. Velusamy ◽  
P. Selvaraj
Keyword(s):  
Structural Integrity ◽  
Fast Breeder Reactor ◽  
Free Level ◽  
Pool Type

Thermal hydraulic investigations of intermediate heat exchanger in a pool-type fast breeder reactor

2008 ◽  
Vol 238 (7) ◽  
pp. 1577-1591 ◽  
Author(s):  
R. Gajapathy ◽  
K. Velusamy ◽  
P. Selvaraj ◽  
P. Chellapandi ◽  
S.C. Chetal ◽  
...  
Keyword(s):  
Heat Exchanger ◽  
Fast Breeder Reactor ◽  
Intermediate Heat Exchanger ◽  
Pool Type

Analysis of Sodium Fire in the Containment Building of Prototype Fast Breeder Reactor Under the Scenario of Core Disruptive Accident

2006 ◽  
Author(s):  
P. M. Rao ◽  
N. Kasinathan ◽  
S. E. Kannan
Keyword(s):  
Structural Integrity ◽  
Peak Pressure ◽  
Safety Issue ◽  
Pressure Rise ◽  
Pool Fire ◽  
Mode Analysis ◽  
Fast Breeder Reactor ◽  
Reactor Assembly ◽  
Computer Codes ◽  
Breeder Reactors

The potential for sodium release to reactor containment building from reactor assembly during Core Disruptive Accident (CDA) in Fast Breeder Reactors (FBR) is an important safety issue with reference to the structural integrity of Reactor Containment Building (RCB). For Prototype Fast Breeder Reactor (PFBR), the estimated sodium release under a CDA of 100 MJ energy release is 350 kg. The ejected sodium reacts easily with air in RCB and causes temperature and pressure rise in the RCB. For estimating the severe thermal consequences in RCB, different modes of sodium fires like pool and spray fires were analyzed by using SOFIRE–II and NACOM sodium fire computer codes. Effects of important parameters like amount of sodium, area of pool, containment air volume and oxygen concentration have been investigated. A peak pressure rise of 7.32 kPa is predicted by SOFIRE II code for 350 kg sodium pool fire in 86,000 m3 RCB volume. Under sodium release as spray followed by unburnt sodium as pool fire mode analysis, the estimated pressure rise is 5.85 kPa in the RCB. In the mode of instantaneous combustion of sodium, the estimated peak pressure rise is 13 kPa.

Study of Thermal-Hydraulic Characteristics during Decay Heat Removal in a Pool-Type Fast Breeder Reactor

1992 ◽  
Vol 98 (1) ◽  
pp. 14-26 ◽  
Author(s):  
Masayoshi Akutsu ◽  
Yoshinobu Okabe ◽  
Kazuziro Satoh ◽  
Hideki Kamide ◽  
Kenji Hayashi ◽  
...  
Keyword(s):  
Heat Removal ◽  
Fast Breeder Reactor ◽  
Hydraulic Characteristics ◽  
Decay Heat ◽  
Pool Type

scholarly journals ICONE15-10233 RADIOACTIVITY TRANSPORTATION IN THE PRIMARY SODIUM CIRCUIT OF POOL TYPE FAST BREEDER REACTOR

2007 ◽  
Vol 2007.15 (0) ◽  
pp. _ICONE1510-_ICONE1510
Author(s):  
Kalyansundaram Sivasubramanian ◽  
S.V.M. Satyanarayana ◽  
Nandagopal Mohankumar
Keyword(s):  
Fast Breeder Reactor ◽  
Pool Type

scholarly journals Stability characteristics of the 500 mw Indian PFBR

2015 ◽  
Vol 30 (2) ◽  
pp. 113-123
Author(s):  
Vijayan Anuraj ◽  
Goverapet Srinivasan ◽  
Kunhiraman Devan
Keyword(s):  
Transient Analysis ◽  
Power Reactor ◽  
Fast Breeder Reactor ◽  
Successful Operation ◽  
Fast Breeder Test Reactor ◽  
Transfer Function Method ◽  
Commercial Scale ◽  
Test Reactor ◽  
The Stability ◽  
Pool Type

After the successful operation of the fast breeder test reactor for over two decades, India is now nearing the completion of a 500 MW (electrical) prototype fast breeder reactor. This commercial scale power reactor is a sodium-cooled, pool-type, mixed-oxide fuelled fast reactor. The stability characteristics of the reactor are an important safety aspect to be studied. In the present work, linear stability of the prototype fast breeder reactor analysis is carried out using the transfer function method, while the stability of the system is checked via the Nyquist criteria. For the completeness of the study, transient analysis with various kinds of reactivity perturbations was carried out. The response of the system in both cases indicated that the system is stable.

Applicability of AE monitoring technique to evaluate structural integrity of fast breeder reactor piping component

1986 ◽  
Vol 94 (3) ◽  
pp. 365-374 ◽  
Author(s):  
T. Kishi ◽  
K. Yamaguchi ◽  
Y. Sakakibara ◽  
I. Komura ◽  
Y. Mori ◽  
...  
Keyword(s):  
Structural Integrity ◽  
Fast Breeder Reactor ◽  
Monitoring Technique

A Study of the Structural Integrity of the Core Support Structure of a Fast Breeder Reactor

1992 ◽  
Vol 100 (1) ◽  
pp. 1-12
Author(s):  
Masahiro Ueta ◽  
Masakazu Ichimiya ◽  
Hiroshi Hirayama ◽  
Masayuki Asano ◽  
Hisaaki Ikeuchi ◽  
...  
Keyword(s):  
Structural Integrity ◽  
Fast Breeder Reactor ◽  
Support Structure ◽  
The Core
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