skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50)

Authors:
;
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1341445
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 94; Journal Issue: C; Related Information: CHORUS Timestamp: 2017-10-04 16:06:05; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United Kingdom
Language:
English

Citation Formats

Odeh, Faisal Y., and Yang, Won Sik. Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50). United Kingdom: N. p., 2016. Web. doi:10.1016/j.anucene.2016.03.011.
Odeh, Faisal Y., & Yang, Won Sik. Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50). United Kingdom. doi:10.1016/j.anucene.2016.03.011.
Odeh, Faisal Y., and Yang, Won Sik. 2016. "Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50)". United Kingdom. doi:10.1016/j.anucene.2016.03.011.
@article{osti_1341445,
title = {Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50)},
author = {Odeh, Faisal Y. and Yang, Won Sik},
abstractNote = {},
doi = {10.1016/j.anucene.2016.03.011},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 94,
place = {United Kingdom},
year = 2016,
month = 8
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.anucene.2016.03.011

Citation Metrics:
Cited by: 1work
Citation information provided by
Web of Science

Save / Share:
  • A liquid-metal fast breeder reactor core design employing seed-blanket-type modular assemblies is presented. The seed region contains PuO/sub 2/-UO/sub 2/ fuel and the blanket region contains depleted UO/sub 2/ fuel. These assemblies constitute the inner core while conventional mixed-oxide assemblies are employed in the outer core region. The results of design studies and analysis show that a large reduction in the sodium void reactivity can be obtained. The core fissile loading is larger than that for a homogeneous core. The analysis of an unprotected loss-of-flow (LOF) accident shows drastically reduced potential for a LOF-driven transient overpower accident. These results andmore » conclusions are similar to those obtained for other heterogeneous core designs.« less
  • A feasibility study on nuclear core design of soluble boron free (SBF) core for small size (150MWth) small modular reactor (SMR) was investigated. The purpose of this study was to design a once through cycle SMR core, where it can be used to supply electricity to a remote isolated area. PWR fuel assembly design with 17×17 arrangement, with 264 fuel rods per assembly was adopted as the basis design. The computer code CASMO-3/MASTER was used for the search of SBF core and fuel assembly analysis for SMR design. A low critical boron concentration (CBC) below 200 ppm core with 4.7more » years once through cycle length was achieved using 57 fuel assemblies having 170 cm of active height. Core reactivity controlled using mainly 512 number of 4 wt% and 960 12 wt% Gd rods.« less
  • The United States and members of the former Soviet Union are expected to ratify a treaty to determine the disposition of an assumed 100 tonnes of excess plutonium from nuclear weapons stockpile reduction. Many options are being considered to safeguard and dispose of this material. A US Department of Energy (DOE)-sponsored fission option study was initiated in which the weapons-grade plutonium is burned in power reactors and converted to a material less suitable for nuclear weapons. The first emphasis of the study was to demonstrate the feasibility of fueling a light water reactor with weapons-grade plutonium as fissionable material. Initialmore » Westinghouse results have been reported to DOE and in previous American Nuclear Society conference papers. The reactor candidate for this task is designated the PDR600, a 600-MW(electric) pressurized water reactor (PWR) with advanced and passive design features. This paper is concerned with core optimization studies performed by Westinghouse Electric Corporation and Westinghouse Savannah River Company.« less
  • To answer the increasing demand for electric power in Japan, very large fast reactors of 10,000 MW(e) unit capacity are expected to make their appearance in due course. The method and results of a design study on a 10,000 MW(e) Liquid Metal Fast Breeder Reactor are described. First, a reference design was obtained for this unprecedented capacity by extrapolating the various characteristics of a 1,000 MW(e) LMFBR. It was found that reactivity increase could be reduced to about 64 when seven subassemblies were voided in the central part of the core, and that the increase of reactivity and the decreasemore » of breeding ratio with time were rather large for the initial loading core. A design optimization procedure was developed based on a complex method of nonlinear programming, amd the method was applied to the very large fast reactor. The process resulted in a relatively large core height and fuel pin diameter, while the power cost was improved due to enhanced breeding gain. The fuel center temperature and the coolant velocity were found close to the upper boundaries of their prescribed ranges. These results concurred qualitatively with calculations using more straightforward optimization techniques. (auth)« less