Abstract: A composite material comprising a first shielding layer (210); at least one metal containing layer (208) over the first shielding layer; and a second shielding layer (206) over said at least one metal containing layer opposite of the first shielding layer; wherein the first shielding layer (210) and the second shielding layer (206) each and/or in combination with other layers of the composite material provide the composite material with radiation shielding characteristics.

Abstract: The invention refers to a method and a device for evaluating the integrity of a control rod material in a nuclear plant. The plant includes a reactor vessel (1), a reactor core (2) that is enclosed in the reactor vessel and formed by a number of nuclear fuel elements (3) and a number of cladding members (4), in which said control material is enclosed, and a circuit (6) that permits a flowing of a fluid through the reactor core and through an external conduit arrangement In order to estimate the integrity of the control material, the value of at least one primary parameter that includes the concentration of a substance, which is released from the control rod material during the operation of the nuclear plant, is determined (21, 23, 28) in said fluid. Furthermore, the value of at least one operational parameter related to said fluid is determined (30, 33, 34, 36).

Abstract: The invention refers to a device for determining the nuclide content of a radioactive fluid. The device comprises a space (2) for receiving the fluid, a primary detector (6) for detection of gamma radiation emitted form the fluid in the space (2), and a processing member (10) for determining the nuclide content of the fluid based on the detected gamma radiation. The primary detector (6) includes a first detector part (8) having a front end directed towards the space and a second detector part (9) arranged adjacent to said front end between the first detector part (8) and the space (2).

Abstract: A device for determining, by detection and calculation, nuclide contents of radioactive inert gases. The device includes a measuring chamber (1) which contains the inert gases, a detector (3) which detects gamma radiation emitted from the radioactive inert gases, calculating members (5) which, based on the detected gamma radiation, calculate the content of the different nuclides.

Abstract: The invention concerns a method and a device for evaluating the integrity of the nuclear fuel in a nuclear plant having a reactor (1) enclosing a reactor core formed by a number of fuel cladding members (2) arranged to enclose said nuclear fuel. The value of each of a number of parameters including activity data (4) of the off-gases from the reactor is determined. The value of each of a number of second parameters including chemical data and activity data of the liquid (5) flowing through the reactor is determined. The value of each of a number of operational parameters (6) including at least one of the reactor effects, control rod position, actual fuel type, flow of off-gases, and flow of the liquid flowing through the reactor is determined. The value of the first and second parameters are standardized (7, 8) in relation to the values of said operational parameters.