Preconceptual design of a sodium component test complex
- 1. Pratt and Whitney Rocketdyne, MS RLA13, P.O. Box 7922, Canoga Park, CA 91309-7922 (United States)
- 2. Argonne National Laboratory, Nuclear Engineering Div., 9700 South Cass Avenue, Argonne, IL 60439-4814 (United States)
- 3. CH2M Hill, 2095 Lakeside Centre Way, Knoxville, TN 37922-6593 (United States)
Description
The U.S. currently lacks a comprehensive sodium testing infrastructure following the demolition of the facilities that previously existed at the Energy Technology Engineering Center (ETEC). It will be essential to establish a new sodium testing infrastructure if the U.S. is to develop and deploy future sodium-cooled advanced fast reactors. The need for testing sodium components such as steam generators, mechanical pumps, electromagnetic pumps, heat exchangers, control rod drive mechanisms, fuel-handling mechanisms, in-service inspection and repair approaches and technologies, and instrumentation, among others has been previously identified. In order to better understand the scope and size of the test facilities needed, a preconceptual design of a Sodium Component Test Complex (SCTC) was initiated to develop a design of sufficient detail to enable reasonable sizing of all facilities and process equipment, to develop reasonably accurate equipment lists and to develop a reasonable estimate of the cost and schedule. This design includes preliminary process flow diagrams (PFDs), preliminary piping and instrumentation diagrams (P and IDs), preliminary electrical single-line diagrams (ELS), preliminary technical and process equipment design, building and equipment layouts and elevations, preliminary operations outlines and an outline for major equipment purchases. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-89448-081-2
- Imprint Title
- Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants - ICAPP '10
- Imprint Pagination
- 2284 p.
- Journal Page Range
- p. 604-614
Conference
- Title
- 2010 International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP '10
- Dates
- 13-17 Jun 2010
- Place
- San Diego, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42099886
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTROL ROD DRIVES; DIAGRAMS; FAST REACTORS; FUEL ELEMENTS; HEAT EXCHANGERS; IN-SERVICE INSPECTION; MANIPULATORS; PUMPS; SODIUM; SODIUM COOLED REACTORS; STEAM GENERATORS; TEST FACILITIES; TESTING
- Descriptors DEC
- ALKALI METALS; BOILERS; ELEMENTS; EPITHERMAL REACTORS; EQUIPMENT; INFORMATION; INSPECTION; LABORATORY EQUIPMENT; LIQUID METAL COOLED REACTORS; MATERIALS HANDLING EQUIPMENT; METALS; REACTOR COMPONENTS; REACTORS; REMOTE HANDLING EQUIPMENT; VAPOR GENERATORS
Optional Information
- Notes
- 1 ref.