DOE-ASME Generation IV Materials Tasks

2006 ◽  
Author(s):  
Timothy E. McGreevy ◽  
Robert I. Jetter
Keyword(s):  
Nuclear Reactor ◽  
Elevated Temperatures ◽  
Future Generation ◽  
Department Of Energy ◽  
Design Codes ◽  
Technology Program ◽  
Program Plan ◽  
American Society

The Department of Energy (DOE) and the American Society of Mechanical Engineers (ASME) wish to update and expand appropriate materials, construction and design codes for application in future Generation IV nuclear reactor systems that operate at elevated temperatures. The scope of interest addresses specific materials and design tasks, all of which are tied to the Generation IV Reactors Integrated Materials Technology Program Plan. Many of the tasks are directly applicable to ASME Section III Subsection NH. The tasks are summarized and discussed with respect to Generation IV needs.

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

2020 ◽  
Vol 6 (4) ◽  
Author(s):  
Robert B. Keating ◽  
Suzanne P. McKillop ◽  
Todd Allen ◽  
Mark Anderson
Keyword(s):  
High Temperature ◽  
Pressure Vessel ◽  
Heat Exchangers ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Department Of Energy ◽  
Research Project ◽  
Compact Heat Exchangers ◽  
High Temperature Reactor ◽  
American Society

Abstract The mission of the U.S. Department of Energy (DOE), Office of Nuclear Energy is to advance nuclear power in order to meet the nation's energy, environmental, and energy security needs. Advanced high temperature reactor systems will require compact heat exchangers (CHXs) for the next generation of nuclear reactors. The DOE is sponsoring research to support the development and deployment of CHXs for use in high temperature advanced reactors. The project is being executed by an Integrated Research Project (IRP) that includes university research institutes, national laboratories, manufacturers, and industry experts. The objective is to enable the use of CHX designs in advanced reactor service. A necessary step for achieving this objective is to ensure that the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 5 has rules for the construction of CHXs for nuclear service. However, construction rules alone are not sufficient to deploy a CHX in an advanced reactor. A strategy for ASME Boiler and Pressure Vessel Code, Section XI, Inservice Inspection (ISI) of a heat exchanger in an operating nuclear reactor will also be required. The purpose of this ASME Code Roadmap is to identify the research gaps impeding the development of suitable construction and ISI rules for CHXs for high temperature reactor service and to provide a framework to utilize the research project results consistent with the expectations and needs of the industry and future owners.

A Review of DOE ECUT Tribology Surveys

1986 ◽  
Vol 108 (4) ◽  
pp. 497-501 ◽  
Author(s):  
L. S. Dake ◽  
J. A. Russell ◽  
D. C. Debrodt
Keyword(s):  
Friction And Wear ◽  
Surface Modifications ◽  
The United States ◽  
Department Of Energy ◽  
Energy Losses ◽  
Research Needs ◽  
Technology Program ◽  
Heat Engines ◽  
The Government ◽  
The U.S

Experts estimate that in 1978 over four quadrillion Btu of energy were lost in the United States because of simple friction and wear. The Energy Conversion and Utilization Technology Program (ECUT) in the U.S. Department of Energy commissioned six surveys from various experts in the field of tribology to learn about the causes of these energy losses and how to reduce them. The surveys included: 1) identification of typical tribology energy sinks in industry, 2) reduction of tribological losses in utilities and transportation, 3) tribological research needed for advanced heat engines, 4) energy conservation potential of new surface modifications, 5) identification of current tribology work sponsored by the government, and 6) an assessment of industrial research needs. A summary of the major findings of each survey is included in this paper.

Characterization of Aluminosilicate Formation on the Surface of a Crystalline Silicotitanate Ion Exchanger

2001 ◽  
Vol 7 (S2) ◽  
pp. 498-499
Author(s):  
J. S. Young ◽  
Y. Su ◽  
L. Li ◽  
M. L. Balmer
Keyword(s):  
Elevated Temperatures ◽  
Operating Conditions ◽  
Department Of Energy ◽  
Ion Exchanger ◽  
Savannah River ◽  
Crystalline Silicotitanate ◽  
High Level ◽  
River Site ◽  
Aluminosilicate Coating

Millions of gallons of high-level radioactive waste are contained in underground tanks at U. S. Department of Energy sites such as Hanford and Savannah River. Most of the radioactivity is due to 137Cs and 90Sr, which must be extracted in order to concentrate the waste. An ion exchanger, crystalline silicotitanate IONSIV® IE911, is being considered for separation of Cs at the Savannah River Site (SRS). While the performance of this ion exchanger has been well characterized under normal operating conditions, Cs removal at slightly elevated temperatures, such as those that may occur in a process upset, is not clear. Our recent study indicates that during exposure to SRS simulant at 55°C and 80°C, an aluminosilicate coating formed on the exchanger surface. There was concern that the coating would affect its ion exchange properties. A LEO 982 field emission scanning electron microscope (FESEM) and an Oxford ISIS energy dispersive x-ray spectrometer (EDS) were used to characterize the coating.

scholarly journals Climate Change Technology Program Plan

Eos ◽  
2006 ◽  
Vol 87 (39) ◽  
pp. 406
Author(s):  
Eugene Bierly
Keyword(s):  
Climate Change ◽  
Technology Program ◽  
Program Plan

scholarly journals New Neutron Imaging Facility development at the Penn State Breazeale Nuclear Reactor

2021 ◽  
Vol 253 ◽  
pp. 04012
Author(s):  
Alibek Kenges ◽  
Kenan Unlu ◽  
Daniel Beck
Keyword(s):  
Neutron Beam ◽  
Nuclear Reactor ◽  
Current System ◽  
Thermal Flux ◽  
Reactor Power ◽  
Neutron Imaging ◽  
Preliminary Results ◽  
Exit Surface ◽  
Penn State ◽  
American Society

Preliminary results of characterization experiments for the New Neutron Imaging Facility (NIF) that is being developed at the Penn State Breazeale Nuclear reactor are presented in the following sections. The methodology of neutron beam characterization described in the American Society for Testing and Materials (ASTM) documents for the neutron imaging systems have been followed to improve the NIF at Penn State to a Category I facility by ASTM designation of quality. Preliminary results showed that our system is capable of producing images of high quality, corresponding to Category I; however, further experiments are needed for full declaration of our facility as such. Additionally, the effective collimation ratio (L/D ratio) of our current system is ∼110 with the capability of improvement to ∼150. The thermal flux at the exit surface of the neutron beam is equal to 5.4 × 106n cm−2s−1 at 1MWth reactor power, which corresponds to the industry comparable value.

scholarly journals Recent Progress on the Standardized DOE Spent Nuclear Fuel Canister

2002 ◽  
Author(s):  
D. Keith Morton ◽  
Spencer D. Snow ◽  
Tom E. Rahl ◽  
Tom J. Hill ◽  
Richard P. Morissette
Keyword(s):  
Nuclear Fuel ◽  
Recent Progress ◽  
Spent Nuclear Fuel ◽  
Transportation Systems ◽  
Pressure Vessels ◽  
Department Of Energy ◽  
Regulatory Agencies ◽  
Spent Fuel ◽  
American Society ◽  
Interim Storage

The Department of Energy (DOE) has developed a set of containers for the handling, interim storage, transportation, and disposal in the national repository of DOE spent nuclear fuel (SNF). This container design, referred to as the standardized DOE SNF canister or standardized canister, was developed by the Department’s National Spent Nuclear Fuel Program (NSNFP) working in conjunction with the Office of Civilian Radioactive Waste Management (OCRWM) and the DOE spent fuel sites. This canister had to have a standardized design yet be capable of accepting virtually all of the DOE SNF, be placed in a variety of storage and transportation systems, and still be acceptable to the repository. Since specific design details regarding the storage, transportation, and repository disposal of DOE SNF were not finalized, the NSNFP recognized the necessity to specify a complete DOE SNF canister design. This allowed other evaluations of canister performance and design to proceed as well as providing standardized canister users adequate information to proceed with their work. This paper is an update of a paper [1] presented to the 1999 American Society of Mechanical Engineers (ASME) Pressure Vessels and Piping (PVP) Conference. It discusses recent progress achieved in various areas to enhance acceptance of this canister not only by the DOE complex but also fabricators and regulatory agencies.

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