Design of advanced integral-type marine reactor, MRX

Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Ishida, Toshihisa; Hoshi, Takashi; Sako, K.

doi:10.1016/s0029-5493(00)00285-5

Cited by 52 publications

(14 citation statements)

References 7 publications

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“…The speed was changed from the original design 1,200 mm/m by evaluating with transient analyses of the MRX. 1) The maximum required torque of the driving motor was calculated to 3Nm from the required drawing force 2.2 kN, the screw lead of the driving shaft 0.6 mm, and the total methe base of measuring of the amount of oxide. 7) For the actual rotor, the magnets of 8 pieces are designed, which are covered by a can to prevent them from oxidation by water.…”

Section: Design Of Driving Motormentioning

confidence: 99%

“…Japan Atomic Energy Research Institute (JAERI) has studied the design of an advanced marine reactor, MRX, 1) with thermal output of 100 MW for the main use of nuclearpowered ship. In general, the reactor power of large scaled pressurized water reactor (PWR) for electricity generation is controlled by a chemical shim and/or control rods in the normal operation.…”

Section: Introductionmentioning

confidence: 99%

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Development of In-vessel Type Control Rod Drive Mechanism for Marine Reactor

Ishida

Imayoshi²,

Yoritsune

et al. 2001

Journal of Nuclear Science and Technology

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A highly reliable control rod drive mechanism (CRDM) installed inside the reactor vessel has developed for use of an advanced marine reactor. This CRDM contributes to compactness and simplicity of the reactor system, and it can eliminate the possibility of a rod ejection accident. The CRDM works in the high temperature and high pressure water-310 • C and 12 MPa, the same atmosphere as the primary loop. Driving force is produced by a synchronous motor with the rotor of a permanent magnet, which has been developed. An innovative latch mechanism using separable ball nuts can latch the driving shaft connecting the control rod and de-latch it for scram. The rod position detector using a magnetostrictive wire type sensor on the principle of Wiedeman effect has been developed, accuracy of which is verified to have a detecting error within 1.2 mm. Ball bearings for thrust and radial supports in rotation have been developed to be capable of working under the high temperature water for a long period. Under condition of high temperature water, the performance tests on latching, de-latching, holding and vertical movement, and durability test were conducted to verify the design conditions. This CRDM can be applied to not only the marine reactor, but also to light water reactors, PWR and BWR.

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Section: Design Of Driving Motormentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Development of In-vessel Type Control Rod Drive Mechanism for Marine Reactor

Ishida

Imayoshi²,

Yoritsune

et al. 2001

Journal of Nuclear Science and Technology

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“…Therefore, the performance of control system for OTSG is demanded urgently to prevent drastic change of system parameters. Many scholars have conducted a lot of research work (Kusunoki et al, 2000;Fausto and Bojan, 2008;Kang and Park, 2008). Hu et al utilized a coordination control system to implement the rapid load following (Hu et al, 2012).…”

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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“…This puts forward higher requirement for the control system design of IPWR system. Hence, many investigators have focused on the study of the load‐following characteristics and stability of the reactor system .…”

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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Design of advanced integral-type marine reactor, MRX

Cited by 52 publications

References 7 publications

Development of In-vessel Type Control Rod Drive Mechanism for Marine Reactor

Development of In-vessel Type Control Rod Drive Mechanism for Marine Reactor

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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