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Title: Nuclear reactor support and seismic restraint with in-vessel core retention cooling features

Abstract

A nuclear reactor including a lateral seismic restraint with a vertically oriented pin attached to the lower vessel head and a mating pin socket attached to the floor. Thermally insulating materials are disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head.

Inventors:
;
Publication Date:
Research Org.:
BWXT mPower, Inc., Charlotte, NC (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1417853
Patent Number(s):
9,875,817
Application Number:
14/299,268
Assignee:
BWXT mPower, Inc. (Charlotte, NC) IDO
DOE Contract Number:
NE0000583
Resource Type:
Patent
Resource Relation:
Patent File Date: 2014 Jun 09
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 42 ENGINEERING

Citation Formats

Edwards, Tyler A., and Edwards, Michael J. Nuclear reactor support and seismic restraint with in-vessel core retention cooling features. United States: N. p., 2018. Web.
Edwards, Tyler A., & Edwards, Michael J. Nuclear reactor support and seismic restraint with in-vessel core retention cooling features. United States.
Edwards, Tyler A., and Edwards, Michael J. 2018. "Nuclear reactor support and seismic restraint with in-vessel core retention cooling features". United States. doi:. https://www.osti.gov/servlets/purl/1417853.
@article{osti_1417853,
title = {Nuclear reactor support and seismic restraint with in-vessel core retention cooling features},
author = {Edwards, Tyler A. and Edwards, Michael J.},
abstractNote = {A nuclear reactor including a lateral seismic restraint with a vertically oriented pin attached to the lower vessel head and a mating pin socket attached to the floor. Thermally insulating materials are disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2018,
month = 1
}

Patent:

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  • If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel lower head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe Pressurized Water Reactor (AP600), which relied upon External Reactor Vessel Coolingmore » (ERVC) for in-vessel retention (IVR), resulted in the United States Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing Light Water Reactors (LWRs). Accordingly, IVR of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors. However, it is not clear that currently-proposed methods to achieve ERVC will provide sufficient heat removal for higher power reactors. A US–Korean International Nuclear Energy Research Initiative (INERI) project has been initiated in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) will determine if IVR is feasible for reactors up to 1500 MWe. This paper summarizes results from the first year of this 3-year project.« less
  • This invention relates to means for cooling the top end of a suspended vessel such as the pressure vessel of a nuclear reactor. The invention consists in supplying a liquid coolant which flows through coils located in contact with an intermediate heat conducting material which is in contact with the top end of the vessel. The liquid coolant or the intermediate liquid may be of liquid metal such as a sodium-potassium alloy and the intermediate material may be contained in a tank rigidly secured to the vessel. In modified arrangements the intermediate material may be a solid or a gas.more » 10 claims, 6 figures.« less