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Title: Fission product transport analysis. Quarterly progress report, April 1--June 30, 1978. [PWR; BWR; primary system reflooding following LOCA]

Abstract

Technical progress during the reporting period has been concerned primarily with continued development of the TRAP-MELT computer code, specification of conditions and code input for meltdown accidents, and initiation of efforts to provide functional design specifications for a fission product transport test facility. The code development efforts were concerned primarily with incorporating the mechanisms into the TRAP-MELT code that allow for particle growth by agglomeration, and adding expressions to give steam viscosity and density up to high temperatures and pressures. To provide a set of conditions for use in developing the code, the needed input for a radionuclide source term was specified by combining best estimate core release fractions with calculated inventories. Technical efforts and results in these areas are discussed individually.

Authors:
; ; ;
Publication Date:
Research Org.:
Battelle Columbus Labs., OH (USA)
OSTI Identifier:
6287897
Alternate Identifier(s):
OSTI ID: 6287897
Report Number(s):
NUREG/CR-0698; BMI-2023
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; LOSS OF COOLANT; MELTDOWN; FISSION PRODUCT RELEASE; MATHEMATICAL MODELS; PWR TYPE REACTORS; COMPUTER CALCULATIONS; CORE FLOODING SYSTEMS; DEPOSITION; FISSION PRODUCTS; PRIMARY COOLANT CIRCUITS; RADIOACTIVITY TRANSPORT; T CODES; ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ECCS; ENGINEERED SAFETY SYSTEMS; ISOTOPES; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 210100 -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Gieseke, J.A., Baybutt, P., Jordan, H., and Jung, R.G. Fission product transport analysis. Quarterly progress report, April 1--June 30, 1978. [PWR; BWR; primary system reflooding following LOCA]. United States: N. p., 1979. Web.
Gieseke, J.A., Baybutt, P., Jordan, H., & Jung, R.G. Fission product transport analysis. Quarterly progress report, April 1--June 30, 1978. [PWR; BWR; primary system reflooding following LOCA]. United States.
Gieseke, J.A., Baybutt, P., Jordan, H., and Jung, R.G. Thu . "Fission product transport analysis. Quarterly progress report, April 1--June 30, 1978. [PWR; BWR; primary system reflooding following LOCA]". United States.
@article{osti_6287897,
title = {Fission product transport analysis. Quarterly progress report, April 1--June 30, 1978. [PWR; BWR; primary system reflooding following LOCA]},
author = {Gieseke, J.A. and Baybutt, P. and Jordan, H. and Jung, R.G.},
abstractNote = {Technical progress during the reporting period has been concerned primarily with continued development of the TRAP-MELT computer code, specification of conditions and code input for meltdown accidents, and initiation of efforts to provide functional design specifications for a fission product transport test facility. The code development efforts were concerned primarily with incorporating the mechanisms into the TRAP-MELT code that allow for particle growth by agglomeration, and adding expressions to give steam viscosity and density up to high temperatures and pressures. To provide a set of conditions for use in developing the code, the needed input for a radionuclide source term was specified by combining best estimate core release fractions with calculated inventories. Technical efforts and results in these areas are discussed individually.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {2}
}

Technical Report:
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