Integrated modular water reactor (IMR) design

Hibi, Koki; Ono, Hitoi; Kanagawa, Takashi

doi:10.1016/j.nucengdes.2003.11.025

Cited by 33 publications

(11 citation statements)

References 2 publications

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“…SMR designs are being developed in Argentina, Brazil, France, Japan, Republic of Korea, Russia, and the United States of America. These SMR designs (Bae et al, 2001;Hibi et al, 2004;Ingersoll, 2009Ingersoll, , 2011Vujić et al, 2012) include CAREM, IMR, SMART, NuScale, Westinghouse SMR, B&W mPower. However, all the SMR designs mentioned above are pressurized water reactors (PWR).…”

Section: Introductionmentioning

confidence: 99%

Novel modular natural circulation BWR design and safety evaluation

Ishii

Shi

Yang

et al. 2015

Annals of Nuclear Energy

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Long fuel cycle design Double passive safety system Design basis accident analysis RELAP5 simulation a b s t r a c tThe 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.

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Section: Introductionmentioning

confidence: 99%

Novel modular natural circulation BWR design and safety evaluation

Ishii

Shi

Yang

et al. 2015

Annals of Nuclear Energy

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“…It is widely used in Integrated Pressurized Water Reactor (IPWR) due to its perfect performance and compact structure (Carelli et al, 2004;Bae et al, 2001;Fukami and Santecchia, 2000;Hibi et al, 2004). For casing once-through steam generator (COTSG), primary coolant flows inside both the inner tube and shell side, secondary fluid flows in the annular channel, and subcooled water is heated to superheated steam by primary coolant.…”

Section: Introductionmentioning

confidence: 99%

Operation characteristic of Integrated Pressurized Water Reactor under coordination control scheme

Xia

Liu

2015

Annals of Nuclear Energy

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“…SMRs usually have attractive characteristics, such as simple structure, enhanced safety and require limited financial resources. Many innovative designs are small‐to‐medium size reactors with integral primary system, such as IRIS, SMART, CAREM, IMR. The SMRs with integral primary system contains reactor coolant and major primary circuit components in reactor vessel.…”

Section: Introductionmentioning

confidence: 99%

“…They have a compact size and without hot leg or cold leg penetrate the reactor vessel, so the safety of reactor system has been greatly improved. Because of the compact configuration, integrated pressurized water reactors (IPWRs) usually be equipped with once‐through type steam generator . The thermal efficiency of secondary‐loop system is improved because the once‐through steam generators (OTSGs) produce superheated steam.…”

Section: Introductionmentioning

confidence: 99%

Analysis of load-following characteristics for an integrated pressurized water reactor

Xia

Peng

2013

Int. J. Energy Res.

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SUMMARYIntegrated pressurized water reactor (IPWR) usually be equipped with once-through steam generators (OTSGs). The OTSG has many advantages such as simple mechanical structure, smaller size, and higher heat transfer efficiency. It produces superheated steam but with less inventory in its secondary side. The steam pressure is easily affected by steam flow rate or feed water flow rate. This draws more attention to design advanced reactor control system. In this paper, a study has been carried out to analyze the thermal hydraulic performance of an advanced IPWR under steady-state and transient conditions by using a thermal hydraulic safety analysis code Relap5. An effective load-following control system is proposed. The steady-state operating characteristics of IPWR at different load conditions show that the average primary coolant temperature, steam pressure, and coolant mass flow rate are the most important control parameters. Pump frequency conversion strategy and OTSG grouping run strategy are used to study the transient operating characteristics of IPWR. Simulation results of the control system demonstrate its capability in regulating feedwater flow rate and reactor power to follow the change of steam flow rate. According to the results, the OTSG grouping run strategy is optimized to ensure the OTSG operates safely under low load conditions.

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Integrated modular water reactor (IMR) design

Cited by 33 publications

References 2 publications

Novel modular natural circulation BWR design and safety evaluation

Novel modular natural circulation BWR design and safety evaluation

Operation characteristic of Integrated Pressurized Water Reactor under coordination control scheme

Analysis of load-following characteristics for an integrated pressurized water reactor

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