ANSI/ANS-8.12-1987(R93): Criticality control of plutonium-uranium mixtures
Creators
- 1. Pacific Northwest National Lab., Richland, WA (United States)
- 2. Los Alamos National Lab., NM (United States)
Description
American National Standards Institute/American Nuclear Society (ANSI/ANS)-8.12-1987(R93) was approved for use on September 11, 1987. The first version of this standard, which only included subcritical limits on homogeneous plutonium-uranium fuel mixtures, was approved July 17, 1978. The current version was revised to include limits on heterogeneous systems as well. This paper provides additional information on the limits presented in the standard. As stated in its forward, the standard open-quotes ... provides guidance for the prevention of criticality accidents in the handling, storing, processing, and transporting of plutonium-uranium fuel mixtures outside reactors and is applicable to all operations involving mixtures of plutonium and natural uranium.close quotes It constitutes an extension of the American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors, ANSI/ANS-8.1-1983. The standard includes subcritical limits for both homogeneous mixtures and heterogeneous lattices of plutonium and uranium. The uranium is assumed to be natural or depleted
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 75
- Journal Page Range
- p. 198b-200.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and the European Nuclear Society (ENS).
- Dates
- 10-14 Nov 1996.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28027952
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S42: ENGINEERING; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICALITY; DEPLETED URANIUM; FUEL SOLUTIONS; HETEROGENEOUS REACTOR CORES; MIXTURES; MODIFICATIONS; NATURAL URANIUM; NUCLEAR FUELS; PLUTONIUM; RADIATION PROTECTION; SAFETY STANDARDS
- Descriptors DEC
- ACTINIDES; DISPERSIONS; ELEMENTS; ENERGY SOURCES; FUELS; LIQUID FUELS; MATERIALS; METALS; REACTOR COMPONENTS; REACTOR CORES; REACTOR MATERIALS; STANDARDS; TRANSURANIUM ELEMENTS; URANIUM
Optional Information
- Secondary number(s)
- CONF-961103--.