Abstract:
본 발명은, 사고 시 원자로냉각재계통의 현열과 노심의 잔열을 제거하도록, 증기발생기의 하부 입구에 연결된 주급수관과 상기 증기발생기의 상부 출구에 연결된 주증기관을 통해 상기 증기발생기로 냉각유체를 순환시키는 피동잔열제거계통에 있어서, 상기 냉각유체의 유량을 기설정된 범위 내로 유지시키도록 잉여 냉각유체를 수용하거나 보충 냉각유체를 공급하는 보충설비를 포함하고, 상기 보충설비는, 상기 냉각유체의 유량에 따라 피동적으로 상기 잉여 냉각유체를 수용하거나 상기 보충 냉각유체를 공급하도록 상기 증기발생기의 하부 입구와 상부 출구 사이의 기설정된 높이에 설치되는 보충탱크; 상기 증기발생기로부터 상기 주증기관으로 토출된 냉각유체를 상기 보충탱크로 흐르게 하는 유로를 형성하도록 상기 주증기관과 상기 보충탱크에 연결되는 제1연결배관; 및 상기 보충탱크로부터 공급되는 보충 냉각유체의 공급 유로를 형성하도록 상기 보충탱크와 상기 주급수관에 연결되는 제2연결배관을 포함하는 피동잔열제거계통을 제공한다.
Abstract:
The invention relates to a canister (1) for final repository of spent fuel elements from a nuclear reactor, comprising an insert (2) that contains said spent fuel elements, an inner copper casing (4a, 4b, 4c) that encloses the insert (2), and at least one outer casing (5a, 5b, 5c) that encloses the copper casing and that consists of a passive-film-forming metal or metal alloy, the passive film on the casing being constituted by an essentially oxidic film that is rich in one or more of the metals in the group of metals that consist of the metals zirconium, chromium and titanium.
Abstract:
The invention provides at least two electrochemical sensors positioned in a nuclear reactor, wherein at least one of the at least two electrochemical sensors has a zirconium electrode, and the at least two electrochemical sensors produce voltages proportional to an electrochemical corrosion potential for a surface that each of the at least two electrochemical sensors are installed upon. The invention also provides an arrangement configured to accept the voltages produced by the at least two electrochemical sensors, wherein the arrangement is configured to determine an electrochemical corrosion potential of a zirconium fuel rod in the nuclear reactor based upon the voltages of the at least two electrochemical sensors.
Abstract:
This invention relates to a method of preparing a nuclear fuel including the step of depositing a coating including silicon nitride bonded silicon carbide on a nuclear fuel surface. The invention extends to a nuclear fuel element (10) and to a nuclear fuel particle (30).
Abstract:
An improved nuclear shielding material based on a resistant organic matrix that is flexible or resilient after room temperature polymerization, and sufficiently fluid before polymerization so as to effectively fill voids in radiation containment structures. The material can be formulated to undergo pyrolysis and transform into a strong ceramic material. Along with the organic matrix the material contains a primary radiation shielding component such as tungsten carbide powder. Additional optional components include: a neutron absorbing/gamma blocking compound such as boron carbide powder, a heat conducting material such as diamond powder, a high temperature resistant compound such as silicon dioxide powder, a second neutron blocking compound which also imparts electrical conductivity, namely barium sulfate powder, and a hydrogen gas surpassing component which readily absorbs hydrogen such as sponge palladium- Refractory materials and rare earth oxides can be included to favor effective ceramic transition.
Abstract:
The invention provides a method for the encapsulation of a nuclear material, which comprises treating the material with an encapsulant, which comprises a cementitious material, such as Portland Cement, and curing, said cementitious material. The method is particularly suitable for the treatment of nuclear fuel materials such as uranium metal, complete Magnox fuel elements, or fuel element debris, for which encapsulation treatments have never previously been known. Such materials may be treated by the method of the invention in order to obtain products which remains stable and monolithic for many hundreds of years, and the invention thereby offers a safe and convenient alternative means of handling other than nuclear fuel reprocessing.
Abstract:
The upper blade (14) of the maintaining spring comprises a flexible branch (18) which is inclined in relation to a lug (15) for fixing the blade of the spring on the upper end part of the fuel assembly, whereby the width thereof can vary according to the length between the fixing lug (15) and a support element (18) of the upper spring blade (14) on the upper plate of the core of the nuclear reactor wherein the fuel assembly is disposed. At least one part of the inclined flexible branch (18) which is situated towards the fixing lug (15) is laterally defined by rectilinear sides (18a, 18b) which are angularly inclined in relation to a longitudinal axis (17) of the spring blade (14) and disposed in a symmetrical manner in relation to the longitudinal axis (17) of the blade (14).
Abstract:
The invention concerns an absorbent pencil comprising a stainless steel sheath (12) closed with plugs (14, 16) and containing a column of absorbent pellets (24) such as boron carbide. It further comprises a terminal hafnium bar (26) fixed to the lower plug by an entirely mechanical linkage.
Abstract:
An absorber body arranged to absorb radiation in a nuclear energy arrangement. The absorber body (1) comprises at least one area (2, 3, 4) with a locally reduced thickness.
Abstract:
A CEDM data acquisition system (40) receives analog coil-current signals from control element drive mechanism coils (18, 20); conditions the analog signals to remove noise induced therein by the electronic circuitry (44) associated with the control element drive mechanisms; digitizes the conditioned analog signals; displays the acquired test data; and records the data for future use. The inventive data acquisition system preferably has the ability to simultaneously measure, display and record coil-current data for all of the five coils associated with each CEDM rod-group with respect to time. Further, the inventive data acquisition system preferably allows the user to monitor, display and record data for up to eight CEDMs simultaneously. It also allows the measurement of rod-drop times during rod-drop testing of the CEDMs.