Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space CraftsSource: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002::page 21006DOI: 10.1115/1.4038774Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Due to the advantages of small volume, light weight, and long-time running, nuclear reactor can provide an ideal energy source for space crafts. In this paper, two small compact prismatic nuclear reactors with different core block materials are presented, which have a thermal power of 5 MW for 10 years of equivalent full power operation. These two reactors use Mo-14%Re alloy or nuclear grade graphite IG110 as core block material, loaded with 50% and 39.5% enriched uranium nitride (UN) fuel and cooled by helium, whose inlet/outlet temperature of the reactor and operational pressure are 850/1300 K and 2 MPa, respectively. High temperature helium flowing out of the reactor can be used as the working medium for closed Brayton cycle power conversion with high efficiency (more than 20%). Neutronics analyses of reactors for the preliminary design in this paper are performed using reactor Monte Carlo (RMC) code developed by Tsinghua University. Both the reactors have enough initial excess reactivity to ensure 10 years of full power operation without refueling, have safety margin for reactor shutdown with one control drum failed, and remain subcritical in the submersion accident. Finally, the two reactors are compared in aspect of the 235U mass and the total reactor mass.
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contributor author | Yang, Xie | |
contributor author | She, Ding | |
contributor author | Shi, Lei | |
date accessioned | 2019-02-28T11:05:49Z | |
date available | 2019-02-28T11:05:49Z | |
date copyright | 3/5/2018 12:00:00 AM | |
date issued | 2018 | |
identifier issn | 2332-8983 | |
identifier other | ners_004_02_021006.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4252635 | |
description abstract | Due to the advantages of small volume, light weight, and long-time running, nuclear reactor can provide an ideal energy source for space crafts. In this paper, two small compact prismatic nuclear reactors with different core block materials are presented, which have a thermal power of 5 MW for 10 years of equivalent full power operation. These two reactors use Mo-14%Re alloy or nuclear grade graphite IG110 as core block material, loaded with 50% and 39.5% enriched uranium nitride (UN) fuel and cooled by helium, whose inlet/outlet temperature of the reactor and operational pressure are 850/1300 K and 2 MPa, respectively. High temperature helium flowing out of the reactor can be used as the working medium for closed Brayton cycle power conversion with high efficiency (more than 20%). Neutronics analyses of reactors for the preliminary design in this paper are performed using reactor Monte Carlo (RMC) code developed by Tsinghua University. Both the reactors have enough initial excess reactivity to ensure 10 years of full power operation without refueling, have safety margin for reactor shutdown with one control drum failed, and remain subcritical in the submersion accident. Finally, the two reactors are compared in aspect of the 235U mass and the total reactor mass. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts | |
type | Journal Paper | |
journal volume | 4 | |
journal issue | 2 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4038774 | |
journal fristpage | 21006 | |
journal lastpage | 021006-5 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002 | |
contenttype | Fulltext |