American National Standard ANSI/ANS-8. 12-1987: Criticality control of plutonium-uranium mixtures

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7265398

Libby, R A; Clayton, E D

American National Standard ANSI/ANS-8.12-1987 was approved for use on September 11, 1987. This paper provides information on the limits presented in the standard. As stated in its foreword, the standard, 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. 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. Limits are provided for a variety of mixtures, including aqueous solutions, dry (H/(Pu+U)=0) mixed oxides at theoretical density, and damp (H/(Pu+U) {le} 0.45) mixed oxides at both theoretical and one-half theoretical density. The limits for homogeneous mixtures shown cover four different plutonium contents (3,8,15, and 30 wt% PuO{sub 2} in PuO{sub 2} + UO{sub 2}) and three different isotopic compositions ({sup 240}Pu > {sup 241}Pu; {sup 240}Pu {ge} 15 wt% and {sup 241}Pu {le} 6 wt%; and {sup 240}Pu {ge} 25 wt% and {sup 241}Pu {le} 15 wt%).

• OSTI ID: 7265398
• Report Number(s): CONF-911107-; CODEN: TANSA; TRN: 92-030814
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics, San Francisco, CA (United States), 10-15 Nov 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
61 RADIATION PROTECTION AND DOSIMETRY
FISSIONABLE MATERIALS
CRITICALITY
SAFETY STANDARDS
PLUTONIUM
STORAGE
TRANSPORT
URANIUM
ALLOY NUCLEAR FUELS
DEPLETED URANIUM
HOMOGENEOUS MIXTURES
HYDROGEN
IFR REACTOR
MATERIALS HANDLING
MIXED OXIDE FUELS
MIXTURES
NATURAL URANIUM
NUCLEAR FUELS
OPERATION
QUANTITY RATIO
REACTOR LATTICES
SUBCRITICALITY
WATER
ZIRCONIUM
ACTINIDES
DISPERSIONS
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FUELS
HYDROGEN COMPOUNDS
MATERIALS
METALS
NONMETALS
OXYGEN COMPOUNDS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SOLID FUELS
STANDARDS
TRANSITION ELEMENTS
TRANSURANIUM ELEMENTS
ZERO POWER REACTORS
420203* - Engineering- Handling Equipment & Procedures
054000 - Nuclear Fuels- Health & Safety
560101 - Biomedical Sciences
Applied Studies- Radiation Effects- Dosimetry & Monitoring- (1992-)