JPS5866400U

JPS5866400U - Nuclear reactor core flow measurement device

Info

Publication number: JPS5866400U
Application number: JP1981161645U
Authority: JP
Inventors: 遠藤　多喜男
Original assignee: 株式会社東芝
Priority date: 1981-10-29
Filing date: 1981-10-29
Publication date: 1983-05-06

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

[Brief explanation of the drawing]

第１図は本考案を沸騰水型原子炉に適用した例を簡略的
に示す原子炉の断面図、第２図は第１図に示された原子
炉の下部に設置される本考案に係る炉心流量測定装置の
一実施例を一部ブ吊ツクで示す断面図、第３図は第２図
の要部を拡大して示す部分的断面図である。１０・・・・・・原子炉圧力容器、１１・・・・・・減
速材タンク、１２・・・・・・炉心部、１４・・・・・
・上部プレナム、１５・・・・・・下部プレナム、１６
・・・・・・（スリーブ状）間隙、１７・・・・・・冷
却材通路、１８・・・・・・インペラ、１９、・・・・
・・インターナルポンプ、２１・・・・・・発電用ター
ビン系、２３・・・・・・タービン、２４・・・・・・
復水器、２８・・・・・・冷却材流量測定装置、３０・
・・・・・測定部、３１・・・・・・変換処理部、３２
・・・・・・演算部、３３・・・・・・表示部、３４・
・・・・・制御部、３６・・・・・・感知部、３７・・
・・・・伝達部、３８・・・・・・測温部、４０・・・
・・・制御棒駆動機構。Figure 1 is a cross-sectional view of a nuclear reactor that simply shows an example in which the present invention is applied to a boiling water reactor, and Figure 2 is a cross-sectional view of the reactor that is installed at the bottom of the reactor shown in Figure 1. FIG. 3 is a partially enlarged cross-sectional view showing an embodiment of the core flow rate measuring device with a partially-hung block. 10... Reactor pressure vessel, 11... Moderator tank, 12... Reactor core, 14...
・Upper plenum, 15...Lower plenum, 16
...... (sleeve-like) gap, 17... Coolant passage, 18... Impeller, 19, ...
... Internal pump, 21 ... Power generation turbine system, 23 ... Turbine, 24 ...
Condenser, 28... Coolant flow rate measuring device, 30.
...Measuring section, 31... Conversion processing section, 32
......Calculating section, 33...Display section, 34.
...Control section, 36...Sensing section, 37...
...Transmission section, 38...Temperature measurement section, 40...
...Control rod drive mechanism.

Claims

[Scope of Claim for Utility Model Registration] 1. Covering the reactor core installed in the reactor pressure vessel with a moderator tank, and forming a sleeve-shaped gap for storing coolant between the moderator tank and the reactor pressure vessel. The lower part of this gap is connected to the lower plenum below the core through a plurality of coolant passages, and an internal pump is installed in the coolant passage, and the inlet and outlet sides of this internal pump are connected to the lower plenum below the core. 1. A reactor core flow rate measuring device, comprising: a coolant flow rate measuring device for measuring a coolant flow rate. 2. The coolant flow rate measurement device includes a measurement unit installed at the inlet and outlet of the internal pump to detect the flow of the coolant in terms of pressure, and a measurement unit to measure the temperature of the coolant flowing into the internal pump. A conversion processing unit that converts the detected differential pressure between the coolant flow and the signals from the temperature measurement unit into electrical signals, and calculates the processed signals to calculate the flow rate distribution of the coolant flowing through the reactor core. A nuclear reactor core flow rate measuring device according to claim 1, which comprises a calculating section for calculating . 3. The coolant flow rate measurement device is a practical device that further includes a display unit that displays the calculation results from the calculation unit, and a control unit that controls the combustion of nuclear fuel in the reactor core and the operation of the pump for converting the coolant flow rate based on the calculation results. A nuclear reactor core flow rate measuring device according to claim 1 or 2 of the patent registration claim.