Response to Severe Changes of Load on the Reactor System of Nuclear Ship Mutsu.

スポンサーリンク

概要

• 論文の詳細を見る

• <BR>The response of the nuclear power system of N. S. Mutsu to severe changes of load have been studied from records taken during the power-raising tests performed on the ship in 1990. The records examined were those involving the most severe load changes foreseen for marine reactors: (a) sharp load increase with total steam flow raised from 25 to 70% rated full flow in 13 s, (b) crash astern maneuver with the position of propulsion turbine command handle changed-taking several seconds-from cruising ahead to STOP, and after about 50s, further changed-taking 30s-to bring the astern propulsion turbine to full speed-to consume approximately 60% rated total steam flow and (c) turbine trip with the ahead turbine intentionally tripped when operating at roughly 100% rated total steam flow. <BR>The foregoing records from load changes-of severity beyond what is foreseen for landbased reactors-proved that the Mutsu reactor is capable of responding smoothly and securely to such severe load changes. These load changes occasioned relatively large mismatches between reactor power supply and steam flow demand, but with notable freedom from any conspicuous overshooting or hunting of the reactor power. This performance can be attributed to (a) correct functioning of the automatic power control system, (b) effective contribution of the self-regulating reactor control property deriving from the large negative feedback between moderator temperature and reactivity, and (c) the ample inventories of coolant in the primary and secondary loops. <BR>The responses to load change are discussed covering those relevant to (a) reactor power, (b) primary loop pressure, and (c) steam generator pressure, with particular reference to the differences seen in response to mild and to severe load changes.

• 一般社団法人 日本原子力学会の論文

著者

• Kusunoki Tsuyoshi

  Japan Atomic Energy Research Institute

• Ochiai Masa-aki

  Japan Atomic Energy Research Institute

• Ishida Toshihisa

  Japan Atomic Energy Research Institut

• Yao Toshiaki

  Ishikawajima-harima Heavy Industries Co. Ltd

• TANAKA Yoshimi

  Ishikawajima-Harima Heavy Industries Co., Ltd.

• INOUE Kimio

  Ishikawajima-Harima Heavy Industries Co., Ltd.

関連論文

• ICONE11-36176 CONTAINMENT PRESSURE SUPPRESSION SYSTEM WITH FUNCTIONS OF WATER INJECTION AND NONCONDENSABLE GAS CONFINEMENT
• Estimates of Collective Doses from a Hypothetical Accident of a Nuclear Submarine
• A111 A nuclear reactor installed in the basement of a building for heat supply(Advanced thermal system analysis-1)
• A106 Safety System of a Submersible Compact Reactor SCR for Under-sea Research Vessel(Nuclear power-1/combustion)
• Experiments of Two-phase Flow Dynamics of Marine Reactor Behavior under Heaving Motion
• ICONE11-36470 CONCEPT OF PASSIVE SAFE SMALL REACTOR FOR DISTRIBUTED ENERGY SUPPLY SYSTEM
• Effects by Sea Wave on Thermal Hydraulics of Marine Reactor System
• H317 DESIGN OF ONE-THROUGH STEAM GENERATOR OF MARINE REACTOR MRX TO COUNTER FLOW INSTABILITY(Heat transfer with phase change)
• Response to Severe Changes of Load on the Reactor System of Nuclear Ship Mutsu.

スポンサーリンク