Published November 1992 | Version v1
Miscellaneous Metadata-only

Aerosols released during large-scale integral MCCI tests in the ACE program

Creators

  • 1. Argonne National Lab., IL (United States)
  • 2. Electric Power Research Inst., Palo Alto, CA (United States)

Description

One of the objectives of the experiments is to collect and characterize all the aerosols released from the MCCIs. Aerosols released from experiments using four types of concrete (siliceous, limestone/common sand, serpentine, and limestone) and a range of metal oxidation for BWR and PWR core material have been collected and characterized. Release fractions were determined for UO2, Zr, the fission-products: BaO, SrO, La2O3, CeO2, MoO2, Te, Ru, and control materials: Ag, In, and B4C. Release fractions of UO2 and the fission products other than Te were small in all tests. However, release of control materials was significant. (orig./HP)

Part of:
Second OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions

Additional details

Publishing Information

Imprint Title
Second OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions
Imprint Pagination
603 p.
Journal Page Range
p. 111-125.
ISSN
0303-4003
Report number
KFK--5108

Conference

Title
2. OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions.
Dates
1-3 Apr 1992.
Place
Karlsruhe (Germany).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
25034341
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CONCRETES; FISSION PRODUCT RELEASE; MELTDOWN; PWR TYPE REACTORS; RADIOACTIVE AEROSOLS; REACTOR SAFETY EXPERIMENTS
Descriptors DEC
ACCIDENTS; AEROSOLS; BUILDING MATERIALS; COLLOIDS; DISPERSIONS; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SOLS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
NEA/CSNI/R--(92)10.