Novel modular natural circulation BWR design and safety evaluation. (November 2015)

• Record Type: Journal Article
• Authors: Ishii, Mamoru; Shi, Shanbin; Yang, Won Sik; Wu, Zeyun; Rassame, Somboon; Liu, Yang
• Is Part Of: Annals of nuclear energy. Volume 85(2015:Nov.)
• Page Start: 220
• Page End: 227
• Publication Date: 2015-11
• Subjects: BWR-type small modular reactor -- Long fuel cycle design -- Double passive safety system -- Design basis accident analysis -- RELAP5 simulation; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2015.05.009
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: Introduction of BWR-type natural circulation small modular reactor preliminary design (NMR-50). Design of long fuel cycle length for the NMR-50. Design of double passive safety systems for the NMR-50. RELAP5 analyses of design basis accidents for the NMR-50. Abstract: The Purdue NMR (Novel Modular Reactor) represents a BWR-type small modular reactor with a significantly reduced reactor pressure vessel (RPV) height. Specifically, it has one third the height of a conventional BWR RPV with an electrical output of 50 MWe. The preliminary design of the NMR-50 including reactor, fuel cycle, and safety systems is described and discussed. The improved neutronics design of the NMR-50 extends the fuel cycle length up to 10 years. The NMR-50 is designed with double passive engineering safety system, which is intended to withstand a prolonged station black out with loss of ultimate heat sink accident such as experienced at Fukushima. In order to evaluate the safety features of the NMR-50, two representative design basis accidents, i.e. main steam line break (MSLB) and bottom drain line break (BDLB), are simulated by using the best-estimate thermal–hydraulic code RELAP5. The RPV water inventory, containment pressure, and the performance of engineering safety systems are investigated for about 33 h after the initiation of the accidents.