LMFBR safety testing needs and the conceptual design of a new safety research experiment facility
Description
A substantial fraction of the US LMFBR safety program is devoted to in-pile testing. Recognition of this has led to continuing studies of the need for new facilities. Based on these studies, ANL is currently engaged in the conceptual design of a new safety testing facility. The need for and the conceptual design of this facility is presented. The study program for in-pile tests considered the following questions: (1) What are the key safety issues that require in-pile testing to be resolved: (2) What types of in-pile experiments are needed to address the key safety issues: (3) What facility functional requirements (e.g. scale, energy requirements, power flatness, etc.) are necessary: (4) What reactor concepts will meet the experimental needs. These studies concluded that new facility capability would be required. This new capability would include testing fuel arrays up to full subassembly size (and possibly larger). A comprehensive screening and evaluation of test reactor concepts was performed to identify the generic types of reactors, and specific concepts within each type which could meet the experimental needs. (Auth.)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 38
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 83-94
- ISSN
- 0029-5493
Conference
- Title
- International seminar on extreme load conditions and limit analysis procedures for structural reactor safeguards and containment structures.
- Dates
- 8 Sep 1975.
- Place
- Berlin, Germany.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 8301861
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LMFBR TYPE REACTORS; LOSS OF FLOW; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SPECIFICATIONS; TEST REACTORS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent