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United Kingdom Atomic Energy Authority - STEP-WP5-Automated DIC Rig
Status: Closed
Published Date: 09/01/2020
Closing Date: 10/02/2020
Value: £100,000
STEP-WP5-Automated DIC Rig - A concept study for a rig that can use DIC to measure deformation under test conditions, to small-scale samples subjected to high-temperature conditions within a vacuum pump enabled environment to demonstrate repeatable testing can be carried out using automated method to ultimately enable rapid material qualification.
Industry: Mechanical installations. - 45350000 Research and development services and related consultancy services. - 73000000 Experimental development services. - 73120000 Development consultancy services. - 73220000
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United Kingdom Atomic Energy Authority - STEP WP5 Uniaxial Rig Concept study
Status: Closed
Published Date: 06/12/2019
Closing Date: 10/01/2020
Value: £100,000
STEP WP5 Uniaxial Rig Concept study - The purpose of this task is produce a Concept Study of a uniaxial mechanical test rig with the capability of subjecting samples to a high magnetic field and high temperatures within a controlled environment (such as under vacuum or purge gas).
Industry: Laboratory, optical and precision equipments (excl. glasses). - 38000000 Industrial or laboratory furnaces, incinerators and ovens. - 42300000 Mechanical installations. - 45350000 Research and development services and related consultancy services. - 73000000 ...and 3 more
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United Kingdom Atomic Energy Authority - STEP WP5 - Fusion Power Plant - Breeder Blanket Design Challenge
Status: Awarded
Published Date: 02/12/2019
Closing Date: 01/11/2019
Value: £180,000
STEP WP5 - Fusion Power Plant - Breeder Blanket Design Challenge - UKAEA wants to identify and partner with Consultant(s) to develop conceptual designs for the breeder blankets of a fusion power plant. Identified Consultant(s) would develop conceptual designs for fusion Breeder Blankets, which are critical systems for future fusion power plants. This system plays an important role in the fuel and thermal cycles of fusion power plants. Breeder Blankets generate fusion fuel and useful heat, which is transferred to the circulated coolant. In many cases this is pressurised and places large loads onto the Breeder Blanket structure. Consultant(s) are requested to submit proposals that address structural and thermal design challenges, applying their expertise to either improve performance, manufacturability and/or Technology Readiness
Industry: Radioactive materials. - 09343000 Industrial process control equipment. - 38810000 Research, testing and scientific technical simulator. - 38970000 Steel pressure vessels. - 44615100 ...and 8 more
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United Kingdom Atomic Energy Authority - STEP WP5 - Heat Pipe Design Challenge
Status: Awarded
Published Date: 29/11/2019
Closing Date: 04/11/2019
Value: £120,000
STEP WP5 - Heat Pipe Design Challenge - Managing the heat exhaust from a fusion reactor is one of the most pressing challenges facing those seeking to realise a commercial power plant design For spherical tokamak designs such as STEP, the compact nature of the device potentially increases the heat fluxes on the plasma-facing components and restricts the space for incorporating cooling when compared to conventional larger aspect-ratio tokamaks such as ITER or EU-DEMO. A fusion reactor heat exhaust is handled via a divertor, which needs to handle large heat fluxes (>10 MW.m-2) especially in the divertor target 2Heat pipes have been proposed as potential technology for fusion high heat flux components since at least 1972. Liquid metal filled heat pipes have been tested under fusion relevant heat fluxes as recently as 2018. Despite this, there remain significant outstanding questions before they can be considered as a feasible solution for the fusion heat exhaust problem The STEP Work Package 5 (Resilient Nuclear Components) wishes to harness industrial expertise in heat pipe design outside the fusion community and to identify whether this expertise can be applied to developing an innovative heat pipe concept design for the STEP divertor target. This design challenge is ultimately concerned with the feasibility of implementation for a heat pipe high heat flux handling solution within the divertor region of a fusion reactor. The UKAEA is seeking the assessment of innovative preliminary concept designs of a high heat flux heat pipe suitable for use as a STEP divertor target. The total duration of the activities of this initial contract shall not exceed 12 weeks and must be completed by March 2020.
Industry: Radioactive materials. - 09343000 Research, testing and scientific technical simulator. - 38970000 Heat-exchange units. - 42511100 Feasibility study, advisory service, analysis. - 71241000 ...and 8 more
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United Kingdom Atomic Energy Authority - STEP WP5 - Stirrer Test Rig Concept Design
Status: Closed
Published Date: 29/11/2019
Closing Date: 03/01/2020
Value: £40,000
STEP WP5 - Stirrer Test Rig Concept Design - To develop further understanding of the performance of materials and coatings in liquid metals and molten salts, we are seeking a Concept Study for a test rig which can investigate coolant corrosive properties and flow behaviour in representative blanket conditions. The intention is to simulate the flow of the coolant, which will be induced by a stirring mechanism (e.g. rotating disk or impeller in a small (less than 100 cm3) crucible).
Industry: Heating-system design services. - 71321200 Corrosion engineering services. - 71337000 Experimental development services. - 73120000 Development consultancy services. - 73220000 ...and 1 more
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United Kingdom Atomic Energy Authority - STEP WP5 - Fusion Power Plant - Diverter Heat Exchanger Design Challenge
Status: Awarded
Published Date: 22/11/2019
Closing Date: 01/11/2019
Value: £180,000
STEP WP5 - Fusion Power Plant - Diverter Heat Exchanger Design Challenge - Manging the heat exhaust from a fusion reactor is one of the most pressing challenges facing those seeking to realise a commercial power plant design. A fusion reactor heat exhaust is handled via a divertor, which needs to handle large heat fluxes (>10 MWm-2) especially in the divertor target. For spherical tokamak designs such as STEP, the compact nature of the device potentially increases the heat fluxes on the plasma-facing components, such as the divertor target, and restricts the space for incorporating cooling when compared to conventional larger aspect-ratio tokamaks such as ITER or EU-DEMO. Parallels can be drawn between the heat management challenges faced in the fusion community and those faced outside the fusion community, particularly in sectors such as motorsport, aerospace, power electronics, and renewable energy where high performance heat exchangers are utilized. The STEP Work Package 5 (Resilient Nuclear Components) wishes to harness industrial expertise in heat exchanger design outside the fusion community and to identify whether this expertise can be applied to developing an innovative heat exchanger concept design for the STEP divertor target.
Industry: Radioactive materials. - 09343000 Research, testing and scientific technical simulator. - 38970000 Heat-exchange units. - 42511100 Feasibility study, advisory service, analysis. - 71241000 ...and 8 more
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CTM Portal for the NDA Shared Services Alliance - Experimental Work on Ruthenium Releases
Status: Closed
Published Date: 15/11/2019
Closing Date: 06/12/2019
Value: £120,000
Experimental Work on Ruthenium Releases - Aim: To quantify the amount of ruthenium released from a non-radioactive solid. Overview of Task: The quantity of ruthenium that is released to the gas phase from a solid that is heated in the region 200-650 °C is to be measured. Four different solids will be assessed. Three of the solids will consist of a large number of element oxides and element nitrates from across the periodic table. Ruthenium is present in the solid at around 1% by elemental mass, but the precise speciation is not known. However, the ruthenium is likely to be in the form of an oxide and/or a nitrate. The quantity of solid available for experiments is not a limiting factor. The presence of nitrates within the solid will mean that upon heating nitrogen oxides (NOx) will be generated, yielding the corresponding element oxide. The 4th solid to be experimented on is RuO2 and will be used as a comparison. This task will be broken down into 4 components for which quotes are requested. The supplier is encouraged to add technical input. Any additional scope is to be quoted for against task 3. The technical scope involves the following tasks: 1. TASK 1 - Scoping Experiments 2. TASK 2 - Main Experimental Work 3. TASK 3 - Opportunity for supplier to suggest technical scope 4. TASK 4 - Secondment of NNL technical staff to assist in part of/all of the experimental program
Industry: Research and experimental development services. - 73100000 Experimental development services. - 73120000
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United Kingdom Atomic Energy Authority - STEP WP5 - Lead-Lithium Flow Loop Concept Study
Status: Closed
Published Date: 07/11/2019
Closing Date: 05/12/2019
Value: £60,000
STEP WP5 - Lead-Lithium Flow Loop Concept Study - To develop further understanding in the United Kingdom and within UKAEA, we are aiming to award a Concept Study contract for a Lead-Lithium flow loop which can investigate fluid properties and flow behaviour in representative blanket conditions.
Industry: Radioactive materials. - 09343000 Magnets. - 31630000 Flowmeters. - 38421110 Pressure gauges. - 38423100 ...and 10 more
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United Kingdom Atomic Energy Authority - STEP WP5 - Heat Pipe Design Challenge
Status: Closed
Published Date: 07/10/2019
Closing Date: 04/11/2019
Value: £120,000
STEP WP5 - Heat Pipe Design Challenge - Managing the heat exhaust from a fusion reactor is one of the most pressing challenges facing those seeking to realise a commercial power plant design For spherical tokamak designs such as STEP, the compact nature of the device potentially increases the heat fluxes on the plasma-facing components and restricts the space for incorporating cooling when compared to conventional larger aspect-ratio tokamaks such as ITER or EU-DEMO. A fusion reactor heat exhaust is handled via a divertor, which needs to handle large heat fluxes (>10 MW.m-2) especially in the divertor target 2Heat pipes have been proposed as potential technology for fusion high heat flux components since at least 1972. Liquid metal filled heat pipes have been tested under fusion relevant heat fluxes as recently as 2018. Despite this, there remain significant outstanding questions before they can be considered as a feasible solution for the fusion heat exhaust problem The STEP Work Package 5 (Resilient Nuclear Components) wishes to harness industrial expertise in heat pipe design outside the fusion community and to identify whether this expertise can be applied to developing an innovative heat pipe concept design for the STEP divertor target. This design challenge is ultimately concerned with the feasibility of implementation for a heat pipe high heat flux handling solution within the divertor region of a fusion reactor. The UKAEA is seeking the assessment of innovative preliminary concept designs of a high heat flux heat pipe suitable for use as a STEP divertor target. The total duration of the activities of this initial contract shall not exceed 12 weeks and must be completed by March 2020.
Industry: Radioactive materials. - 09343000 Research, testing and scientific technical simulator. - 38970000 Heat-exchange units. - 42511100 Feasibility study, advisory service, analysis. - 71241000 ...and 8 more
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United Kingdom Atomic Energy Authority - STEP WP5 - Fusion Power Plant - Diverter Heat Exchanger Design Challenge
Status: Closed
Published Date: 04/10/2019
Closing Date: 01/11/2019
Value: £180,000
STEP WP5 - Fusion Power Plant - Diverter Heat Exchanger Design Challenge - Manging the heat exhaust from a fusion reactor is one of the most pressing challenges facing those seeking to realise a commercial power plant design. A fusion reactor heat exhaust is handled via a divertor, which needs to handle large heat fluxes (>10 MWm-2) especially in the divertor target. For spherical tokamak designs such as STEP, the compact nature of the device potentially increases the heat fluxes on the plasma-facing components, such as the divertor target, and restricts the space for incorporating cooling when compared to conventional larger aspect-ratio tokamaks such as ITER or EU-DEMO. Parallels can be drawn between the heat management challenges faced in the fusion community and those faced outside the fusion community, particularly in sectors such as motorsport, aerospace, power electronics, and renewable energy where high performance heat exchangers are utilized. The STEP Work Package 5 (Resilient Nuclear Components) wishes to harness industrial expertise in heat exchanger design outside the fusion community and to identify whether this expertise can be applied to developing an innovative heat exchanger concept design for the STEP divertor target.
Industry: Radioactive materials. - 09343000 Research, testing and scientific technical simulator. - 38970000 Heat-exchange units. - 42511100 Feasibility study, advisory service, analysis. - 71241000 ...and 8 more
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