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Title: SIEX: a correlated code for the prediction of liquid metal fast breeder reactor (LMFBR) fuel thermal performance

Authors:
;
Publication Date:
Research Org.:
Hanford Engineering Development Lab., Richland, Wash. (USA)
OSTI Identifier:
4181413
Report Number(s):
HEDL-TME-74-55
NSA Number:
NSA-32-016269
DOE Contract Number:
AT(45-1)-2170
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-75
Country of Publication:
United States
Language:
English
Subject:
N77500* -Reactors-Power Reactors, Breeding; *COMPUTER CODES- S CODES; *FUEL PINS- PERFORMANCE; *LMFBR TYPE REACTORS- FUEL PINS; BURNUP; DEFORMATION; FISSION PRODUCT RELEASE; HEAT TRANSFER; NEUTRON FLUX; PLUTONIUM DIOXIDE; POWER DISTRIBUTION; TEMPERATURE DISTRIBUTION; URANIUM DIOXIDE

Citation Formats

Dutt, D S, and Baker, R B. SIEX: a correlated code for the prediction of liquid metal fast breeder reactor (LMFBR) fuel thermal performance. United States: N. p., 1975. Web. doi:10.2172/4181413.
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Dutt, D S, & Baker, R B. SIEX: a correlated code for the prediction of liquid metal fast breeder reactor (LMFBR) fuel thermal performance. United States. doi:10.2172/4181413.
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Dutt, D S, and Baker, R B. Sun . "SIEX: a correlated code for the prediction of liquid metal fast breeder reactor (LMFBR) fuel thermal performance". United States. doi:10.2172/4181413. https://www.osti.gov/servlets/purl/4181413.
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@article{osti_4181413,
title = {SIEX: a correlated code for the prediction of liquid metal fast breeder reactor (LMFBR) fuel thermal performance},
author = {Dutt, D S and Baker, R B},
abstractNote = {},
doi = {10.2172/4181413},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jun 01 00:00:00 EDT 1975},
month = {Sun Jun 01 00:00:00 EDT 1975}
}
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Technical Report:
View Technical Report (3.58 MB)
DOI:  10.2172/4181413
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  • ;
    The SIEX computer program is a steady state heat transfer code developed to provide thermal performance calculations for a mixed-oxide fuel element in a fast neutron environment. Fuel restructuring, fuel-cladding heat conduction and fission gas release are modeled to provide assessment of the temperatures. Modeling emphasis has been placed on correlations to measurable quantities from EBR-II irradiation tests and the inclusion of these correlations in a physically based computational scheme. SIEX is completely modular in construction allowing the user options for material properties and correlated models. Required code input is limited to geometric and environmental parameters, with a ``consistant`` setmore » of material properties and correlated models provided by the code. The development of physically based correlations to model certain of the phenomana has resulted in a computer program which provides reliable estimates of thermal performance characteristics, yet requires a small amount of core storage and computer running time.« less

  • velopments and schedules required for an orderly and efficient demonstration of fuel-recycle technology adequate to facilitate the growth of a viable LMFBR-power industry. The scope of the program for the Fuel Recycle Element is that portion of the fuel cycle between removal of partially spent fuel and blanket material from the rcactor site and return to the reactor site of newly fabricated fuel and blanket assemblies. Operations in the fuel cycle include shipping, reprocessing, preparation and fabrication, fuel materials management, and management of wastes. Also included in the Fuel Recycle Elements are the general fuel-cycle studies pertinent to all ofmore » the fuel-recycle operations, -- e.g., studies of economics, siting criteria for reprocessing plants, safety, fuel accountability, liability risks, safeguards, and government licensing and regulation. Two important responsibilities of the Fuel Recycle programs are the demonstration of commercial fabrication capabilities for initial cores, and the development and demonstration of quality assurance technology to permit industry to fabricate fuel which can meet LMFBR-design objectives. (auth)« less

  • In FY-76, Task 3 of Contract E(04-3)-893 consisted of the following programs: fuel rod chemistry and thermodynamics; fuel rod engineering; fuel irradiations testing and analysis; and reference structural materials. Starting in FY-77, the Fuel Rod Engineering Program was reorganized into other existing G.E. programs under the E(04-3)-893 contract. Continuation of the reports on technical progress of this program can be found under 189 No. SG009, Task 3, or 189 No. SG023, Task 11.