The Criticality Safety Analysis of the Spent Fuel Storage Pool Area I in Small Modular Reactor

Article Preview

Abstract:

Based on the Monte Carlo calculation method, geometric model of spent fuel storage pool Area I of small modular reactor is established, assuming infinite 6×6 type storage racks. Calculation results show that the reactivity is maximal when the water density is 1.0g/cm3. The value of keff is 0.8729 in normal storage condition. The spacing of storage racks in spent fuel pool would change in an earthquake accident condition. The values of reactivity of spent fuel pool in the assumed earthquake accident condition are also calculated. The values of keff are between 0.872 and 0.876. Both in normal condition and assumed earthquake accident condition, the values of keff are less than 0.95, to meet nuclear safety regulatory requirements.

You might also be interested in these eBooks

Info:

Periodical:

Advanced Materials Research (Volumes 986-987)

Pages:

589-592

Citation:

Online since:

July 2014

Export:

Price:

Permissions CCC:

Permissions PLS:

Сopyright:

© 2014 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

* - Corresponding Author

[1] Los Alamos National Laboratory, MCNP—A General Monte Carlo N-Particle Transport Code.

Google Scholar

[2] HAF102 Nuclear Power Plant Design and Safety Requirements, (2004).

Google Scholar

[3] HAD102/15 Nuclear Power Plant Fuel Handling and Storage Systems, (2007).

Google Scholar

[4] GB15146-2008 Nuclear Criticality Safety of Fissile Materials Outside Reactors, (2008).

Google Scholar

[5] RCC-P Design and Construction Rules for System Design of 900 MW PWR Nuclear Power Plants, 1991 (amended in 1995).

Google Scholar