NSUF 15-558: Proton Irradiations of Alloys Fabricated by Powder Metallurgy and Hot Isostatic Pressing
The objective of this project is to assess the viability of using alloys manufactured by powder metallurgy and hot isostatic pressing (PM-HIP) for nuclear reactor internals, which would enhance the weldability and inspectability of these components. Recently, alloys produced by PM-HIP have been developed and introduced for pressure-retaining applications in the electric power industry. These PM-HIP components exhibit excellent structural uniformity, no chemical segregation, superior mechanical properties, and enhanced weldability. In addition, PM-HIP components are produced near-net shape, which offers the distinct advantages of minimizing machining and enhancing the ease of inspectability of the component. Because of these exceptional properties, PM-HIP alloys are of interest to the nuclear power industry as potential structural materials for LWRs, advanced light water reactors (ALWRs), small modular reactors (SMRs), and advanced (e.g. Generation IV) reactors. But little is known about the irradiation response of PM-HIP alloys, particularly in comparison to that of conventional alloys. This project seeks to understand these irradiation effects. This project will conduct a systematic proton irradiation campaign of PM-HIP and conventional alloys, to enable a side-by-side comparison of their irradiation response. Alloys to be studied are austenitic stainless steels 304L and 316L, Alloys 625 and 690, ferritic steel Grade 91, and pressure vessel steel SA508 Class 1 Grade 3. All alloys will be prepared by PM-HIP and either casting or forging. This project will conduct the following irradiations at the Michigan Ion Beam Laboratory (MIBL): (1) Set #1, 2.0 MeV protons, 3 dpa, 400°C (2) Set #2, 2.0 MeV protons, 3 dpa, 400°C (3) Set #2, 2.0 MeV protons, 5 dpa, 400°C (but we are open to lower dose if cost is an issue) (4) Set #2, 2.0 MeV protons, 3 dpa, 500°C Improving the manufacturing processes for reactor internals will have broad impact across all DOE-NE programs. This project will compare the irradiation response of PM-HIP to conventionally manufactured forms of several families of alloys commonly used in LWR internals, or which are candidates for ALWR and SMR internals. Therefore, this project will produce results relevant to the DOE-NE base programs on Light Water Reactor Technologies, Advanced Reactor Technologies, Space Power Systems, and Small Modular Reactor Technologies. This project will supplement ongoing DOE NEET research on Innovative Manufacturing Process for Nuclear Power Plant Components via Powder Metallurgy and Hot Isostatic Processing Methods (DE-NE000054). This project will be completed by Fall 2015.
Additional Info
| Field | Value |
|---|---|
| Abstract | The objective of this project is to assess the viability of using alloys manufactured by powder metallurgy and hot isostatic pressing (PM-HIP) for nuclear reactor internals, which would enhance the weldability and inspectability of these components. Recently, alloys produced by PM-HIP have been developed and introduced for pressure-retaining applications in the electric power industry. These PM-HIP components exhibit excellent structural uniformity, no chemical segregation, superior mechanical properties, and enhanced weldability. In addition, PM-HIP components are produced near-net shape, which offers the distinct advantages of minimizing machining and enhancing the ease of inspectability of the component. Because of these exceptional properties, PM-HIP alloys are of interest to the nuclear power industry as potential structural materials for LWRs, advanced light water reactors (ALWRs), small modular reactors (SMRs), and advanced (e.g. Generation IV) reactors. But little is known about the irradiation response of PM-HIP alloys, particularly in comparison to that of conventional alloys. This project seeks to understand these irradiation effects. This project will conduct a systematic proton irradiation campaign of PM-HIP and conventional alloys, to enable a side-by-side comparison of their irradiation response. Alloys to be studied are austenitic stainless steels 304L and 316L, Alloys 625 and 690, ferritic steel Grade 91, and pressure vessel steel SA508 Class 1 Grade 3. All alloys will be prepared by PM-HIP and either casting or forging. This project will conduct the following irradiations at the Michigan Ion Beam Laboratory (MIBL): (1) Set #1, 2.0 MeV protons, 3 dpa, 400°C (2) Set #2, 2.0 MeV protons, 3 dpa, 400°C (3) Set #2, 2.0 MeV protons, 5 dpa, 400°C (but we are open to lower dose if cost is an issue) (4) Set #2, 2.0 MeV protons, 3 dpa, 500°C Improving the manufacturing processes for reactor internals will have broad impact across all DOE-NE programs. This project will compare the irradiation response of PM-HIP to conventionally manufactured forms of several families of alloys commonly used in LWR internals, or which are candidates for ALWR and SMR internals. Therefore, this project will produce results relevant to the DOE-NE base programs on Light Water Reactor Technologies, Advanced Reactor Technologies, Space Power Systems, and Small Modular Reactor Technologies. This project will supplement ongoing DOE NEET research on Innovative Manufacturing Process for Nuclear Power Plant Components via Powder Metallurgy and Hot Isostatic Processing Methods (DE-NE000054). This project will be completed by Fall 2015. |
| Award Announced Date | 2015-04-22T00:00:00 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Kevin Field |
| Irradiation Facility | None |
| PI | Janelle Wharry |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 558 |