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Title: Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan

Abstract

In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safety initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertaintiesmore » about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary “end user” of the results from this DOE-sponsored work. The response to the Fukushima accident has been global, and there is a continuing multinational interest in collaborations to better quantify accident consequences and to incorporate lessons learned from the accident. DOE will continue to seek opportunities to facilitate collaborations that are of value to the U.S. industry, particularly where the collaboration provides access to vital data from the accident or otherwise supports or leverages other important R&D work. The purpose of the Reactor Safety Technology R&D is to improve understanding of beyond design basis events and reduce uncertainty in severe accident progression, phenomenology, and outcomes using existing analytical codes and information gleaned from severe accidents, in particular the Fukushima Daiichi events. This information will be used to aid in developing mitigating strategies and improving severe accident management guidelines for the current light water reactor fleet.« less

Authors:
 [1];  [2];  [3];  [4];  [5];  [5];  [6];  [7];  [7]
  1. Univ. of Wisconsin, Madison, WI (United States)
  2. US Dept. of Energy, Washington, DC (United States)
  3. Argonne National Lab. (ANL), Argonne, IL (United States)
  4. Rempe and Associates LLC, Idaho Falls, ID (United States)
  5. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  6. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  7. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1369624
Report Number(s):
INL/EXT-15-35976 (Revision 1)
M2LW-15IN1006085, M3LW-17AN1006102, INL/EXT-15-35976 (Revision 1); TRN: US1702257
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; SEVERE ACCIDENTS; REACTOR SAFETY; WATER MODERATED REACTORS; REACTOR ACCIDENTS; NUCLEAR INDUSTRY; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; NUCLEAR POWER PLANTS; WATER COOLED REACTORS; ACCIDENT MANAGEMENT; REACTOR TECHNOLOGY; Pathway Plan; Reactor; Safety; Technology

Citation Formats

Corradini, M. L., Peko, D., Farmer, M., Rempe, J., Humrickhouse, P., O'Brien, J., Robb, K., Gauntt, R., and Osborn, D. Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan. United States: N. p., 2016. Web. doi:10.2172/1369624.
Corradini, M. L., Peko, D., Farmer, M., Rempe, J., Humrickhouse, P., O'Brien, J., Robb, K., Gauntt, R., & Osborn, D. Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan. United States. doi:10.2172/1369624.
Corradini, M. L., Peko, D., Farmer, M., Rempe, J., Humrickhouse, P., O'Brien, J., Robb, K., Gauntt, R., and Osborn, D. Wed . "Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan". United States. doi:10.2172/1369624. https://www.osti.gov/servlets/purl/1369624.
@article{osti_1369624,
title = {Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan},
author = {Corradini, M. L. and Peko, D. and Farmer, M. and Rempe, J. and Humrickhouse, P. and O'Brien, J. and Robb, K. and Gauntt, R. and Osborn, D.},
abstractNote = {In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safety initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertainties about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary “end user” of the results from this DOE-sponsored work. The response to the Fukushima accident has been global, and there is a continuing multinational interest in collaborations to better quantify accident consequences and to incorporate lessons learned from the accident. DOE will continue to seek opportunities to facilitate collaborations that are of value to the U.S. industry, particularly where the collaboration provides access to vital data from the accident or otherwise supports or leverages other important R&D work. The purpose of the Reactor Safety Technology R&D is to improve understanding of beyond design basis events and reduce uncertainty in severe accident progression, phenomenology, and outcomes using existing analytical codes and information gleaned from severe accidents, in particular the Fukushima Daiichi events. This information will be used to aid in developing mitigating strategies and improving severe accident management guidelines for the current light water reactor fleet.},
doi = {10.2172/1369624},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {6}
}

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