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Title: Analytical methods in the high conversion reactor core design

Abstract

High conversion reactor (HCR) design methods have been used at the Technical University of Braunschweig (TUBS) with the technological support of Kraftwerk Union (KWU). The present state and objectives of this cooperation between KWU and TUBS in the field of HCRs have been described using existing design models and current activities aimed at further development and validation of the codes. The hard physical and thermal-hydraulic boundary conditions of pressurized water reactor (PWR) cores with a high degree of fuel utilization result from the tight packing of the HCR fuel rods and the high fissionable plutonium content of the fuel. In terms of design, the problem will be solved with rod bundles whose fuel rods are adjusted by helical spacers to the proposed small rod pitches. These HCR properties require novel computational models for neutron physics, thermal hydraulics, and fuel rod design. By means of a survey of the codes, the analytical procedure for present-day HCR core design is presented. The design programs are currently under intensive development, as design tools with a solid, scientific foundation and with essential parameters that are widely valid and are required for a promising optimization of the HCR core. Design results and a survey ofmore » future HCR development are given. In this connection, the reoptimization of the PWR core in the direction of an HCR is considered a fascinating scientific task, with respect to both economic and safety aspects.« less

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Technische Universitat Braunschweig, Institut fur Raumflug- und Reaktortechnik, Hans-Sommer-Str. 5, D-3300 Braunschweig (DE)
OSTI Identifier:
7226398
Alternate Identifier(s):
OSTI ID: 7226398
Resource Type:
Journal Article
Journal Name:
Nucl. Technol.; (United States)
Additional Journal Information:
Journal Volume: 80:2
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; PWR TYPE REACTORS; REACTOR CORES; COMPUTER-AIDED DESIGN; BURNUP; COMPUTER CODES; DENSITY; DESIGN; ECONOMICS; FUEL RODS; HYDRAULICS; NEUTRON FLUX; NUCLEAR FUELS; PERFORMANCE; REACTOR PHYSICS; REACTOR SAFETY; ROD BUNDLES; THERMODYNAMICS; ENERGY SOURCES; FLUID MECHANICS; FUEL ELEMENTS; FUELS; MATERIALS; MECHANICS; PHYSICAL PROPERTIES; PHYSICS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 990220 -- Computers, Computerized Models, & Computer Programs-- (1987-1989)

Citation Formats

Zeggel, W., Oldekop, W., Axmann, J.K., Bethke, S., Moldaschl, H., Ulrych, G., and Berger, H.D. Analytical methods in the high conversion reactor core design. United States: N. p., 1988. Web.
Zeggel, W., Oldekop, W., Axmann, J.K., Bethke, S., Moldaschl, H., Ulrych, G., & Berger, H.D. Analytical methods in the high conversion reactor core design. United States.
Zeggel, W., Oldekop, W., Axmann, J.K., Bethke, S., Moldaschl, H., Ulrych, G., and Berger, H.D. Mon . "Analytical methods in the high conversion reactor core design". United States.
@article{osti_7226398,
title = {Analytical methods in the high conversion reactor core design},
author = {Zeggel, W. and Oldekop, W. and Axmann, J.K. and Bethke, S. and Moldaschl, H. and Ulrych, G. and Berger, H.D.},
abstractNote = {High conversion reactor (HCR) design methods have been used at the Technical University of Braunschweig (TUBS) with the technological support of Kraftwerk Union (KWU). The present state and objectives of this cooperation between KWU and TUBS in the field of HCRs have been described using existing design models and current activities aimed at further development and validation of the codes. The hard physical and thermal-hydraulic boundary conditions of pressurized water reactor (PWR) cores with a high degree of fuel utilization result from the tight packing of the HCR fuel rods and the high fissionable plutonium content of the fuel. In terms of design, the problem will be solved with rod bundles whose fuel rods are adjusted by helical spacers to the proposed small rod pitches. These HCR properties require novel computational models for neutron physics, thermal hydraulics, and fuel rod design. By means of a survey of the codes, the analytical procedure for present-day HCR core design is presented. The design programs are currently under intensive development, as design tools with a solid, scientific foundation and with essential parameters that are widely valid and are required for a promising optimization of the HCR core. Design results and a survey of future HCR development are given. In this connection, the reoptimization of the PWR core in the direction of an HCR is considered a fascinating scientific task, with respect to both economic and safety aspects.},
doi = {},
journal = {Nucl. Technol.; (United States)},
number = ,
volume = 80:2,
place = {United States},
year = {1988},
month = {2}
}