Fukushima accident has raised a strong concern and apprehension about the safety of a nuclear reactor failing to remove the decay heat following an extreme event. After Fukushima accident, the reactor designers worldwide analyzed the safety margin of the existing and new generation nuclear power plants for such an event. Advanced heavy water reactor (AHWR), designed in India, was also analyzed for even more severe conditions than occurred at Fukushima. AHWR equipped with several passive systems showed its robustness against this type of scenarios. However, several new passive systems were incorporated in AHWR design for maintaining the integrity of the reactor at least for 7 days as a grace period. A passive moderator cooling system (PMCS) and a passive endshield cooling system (PECS) were among the newly introduced safety system in AHWR. An experimental test facility simulating the prolonged station blackout (SBO) case in AHWR has been designed and built. Experiments have been performed in the test facility for simulated conditions of prolonged SBO. The current study shows the performance of AHWR during prolonged SBO case through simulation in the integral test facility. The results indicate that AHWR design is capable of removing decay heat for prolonged period without operator interference.

References

References
1.
Sinha
,
R. K.
, and
Kakodkar
,
A.
,
2006
, “
Design and Development of the AHWR—The Indian Thorium Fuelled Innovative Nuclear Reactor
,”
Nucl. Eng. Des.
,
236
(
7–8
), pp.
683
700
.
2.
Kumar
,
M.
,
Nayak
,
A. K.
,
Jain
,
V.
,
Vijayan
,
P. K.
, and
Vaze
,
K. K.
,
2013
, “
Managing a Prolonged Station Blackout Condition in AHWR by Passive Means
,”
Nucl. Eng. Technol.
,
45
(5), pp. 605–612.
3.
Kumar
,
M.
,
Pal
,
E.
,
Nayak
,
A. K.
, and
Vijayan
,
P. K.
,
2015
, “
Conceptual Design of Passive Moderator Cooling System for a Pressure Tube Type Natural Circulation Boiling Water Cooled Reactor
,”
Nucl. Eng. Des.
,
291
, pp.
261
270
.
4.
Ishii
,
M.
, and
Kataoka
,
I.
,
1983
, “
Similarity Analysis and Scaling Criteria for LWRs Under Single-Phase and Two-Phase Natural Circulation
,” Argonne National Laboratory, Lemont, IL, Report No.
NUREG/CR-3267
.https://inis.iaea.org/search/search.aspx?orig_q=RN:14779008
5.
Ishii
,
M.
,
Revankar
,
S. T.
,
Leonardi
,
T.
,
Dowlati
,
R.
,
Bertodano
,
M. L.
, and
Babelli
,
I.
,
1998
, “
The Three-Level Scaling Approach With Application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA)
,”
Nucl. Eng. Des.
,
186
(
1–2
), pp.
177
211
.
You do not currently have access to this content.