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Title: Demonstration of optimum fuel-to-moderator ratio in a PWR unit fuel cell

Abstract

Nuclear engineering students at The Pennsylvania State University develop scaled-down [[approx]350 MW(thermal)] pressurized water reactors (PWRs) using actual plants as references. The design criteria include maintaining the clad temperature below 2200[degree]F, fuel temperature below melting point, sufficient departure from nucleate boiling ratio (DNBR) margin, a beginning-of-life boron concentration that yields a negative moderator temperature coefficient, an adequate cycle power production (330 effective full-power days), and a batch loading scheme that is economical. The design project allows for many degrees of freedom (e.g., assembly number, pitch and height and batch enrichments) so that each student's result is unique. The iterative nature of the design process is stressed in the course. The LEOPARD code is used for the unit cell depletion, critical boron, and equilibrium xenon calculations. Radial two-group diffusion equations are solved with the TWIDDLE-DEE code. The steady-state ZEBRA thermal-hydraulics program is used for calculating DNBR. The unit fuel cell pin radius and pitch (fuel-to-moerator ratio) for the scaled-down design, however, was set equal to the already optimized ratio for the reference PWR. This paper describes an honors project that shows how the optimum fuel-to-moderator ratio is found for a unit fuel cell shown in terms of neutron economics. This exercisemore » illustrates the impact of fuel-to-moderator variations on fuel utilization factor and the effect of assuming space and energy separability.« less

Authors:
;  [1]
  1. (Pennsylvania State Univ., University Park (United States))
Publication Date:
OSTI Identifier:
6684476
Alternate Identifier(s):
OSTI ID: 6684476
Report Number(s):
CONF-921102--
Journal ID: ISSN 0003-018X; CODEN: TANSAO
Resource Type:
Conference
Journal Name:
Transactions of the American Nuclear Society; (United States)
Additional Journal Information:
Journal Volume: 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; Journal ID: ISSN 0003-018X
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; MODERATOR-FUEL RATIO; BORON; COMPUTER CALCULATIONS; L CODES; T CODES; Z CODES; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SEMIMETALS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS 210200* -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Feltus, M.A., and Pozsgai, C. Demonstration of optimum fuel-to-moderator ratio in a PWR unit fuel cell. United States: N. p., 1992. Web.
Feltus, M.A., & Pozsgai, C. Demonstration of optimum fuel-to-moderator ratio in a PWR unit fuel cell. United States.
Feltus, M.A., and Pozsgai, C. Wed . "Demonstration of optimum fuel-to-moderator ratio in a PWR unit fuel cell". United States.
@article{osti_6684476,
title = {Demonstration of optimum fuel-to-moderator ratio in a PWR unit fuel cell},
author = {Feltus, M.A. and Pozsgai, C.},
abstractNote = {Nuclear engineering students at The Pennsylvania State University develop scaled-down [[approx]350 MW(thermal)] pressurized water reactors (PWRs) using actual plants as references. The design criteria include maintaining the clad temperature below 2200[degree]F, fuel temperature below melting point, sufficient departure from nucleate boiling ratio (DNBR) margin, a beginning-of-life boron concentration that yields a negative moderator temperature coefficient, an adequate cycle power production (330 effective full-power days), and a batch loading scheme that is economical. The design project allows for many degrees of freedom (e.g., assembly number, pitch and height and batch enrichments) so that each student's result is unique. The iterative nature of the design process is stressed in the course. The LEOPARD code is used for the unit cell depletion, critical boron, and equilibrium xenon calculations. Radial two-group diffusion equations are solved with the TWIDDLE-DEE code. The steady-state ZEBRA thermal-hydraulics program is used for calculating DNBR. The unit fuel cell pin radius and pitch (fuel-to-moerator ratio) for the scaled-down design, however, was set equal to the already optimized ratio for the reference PWR. This paper describes an honors project that shows how the optimum fuel-to-moderator ratio is found for a unit fuel cell shown in terms of neutron economics. This exercise illustrates the impact of fuel-to-moderator variations on fuel utilization factor and the effect of assuming space and energy separability.},
doi = {},
journal = {Transactions of the American Nuclear Society; (United States)},
issn = {0003-018X},
number = ,
volume = 66,
place = {United States},
year = {1992},
month = {1}
}

Conference:
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