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Title: OECD MCCI Project 2-D Core Concrete Interaction (CCI) Tests. CCI-5 Test Plan. Rev. 1, Final

Abstract

Ex-vessel debris coolability is an important light water reactor (LWR) safety issue. For existing plants, resolution of this issue will confirm the technical basis for severe accident management guidelines (SAMGs). For new reactors, understanding this issue will help confirm the effectiveness of the design and implementation of new accident mitigation features and severe accident management design alternatives (SAMDAs). The first OECD-MCCI program conducted reactor material experiments focused on achieving the following technical objectives: (i) provide confirmatory evidence for various cooling mechanisms through separate effect tests and data for severe accident code model development, and (ii) provide longer-term two-dimensional core-concrete interaction data for code assessment and improvement. Debris cooling mechanisms investigated as part of the first MCCI program included: (i) water ingression through cracks/fissures in the core debris, (ii) melt eruption caused by gas sparging (volcanic-type event), and (iii) large-scale crust mechanical failure leading to renewed bulk cooling. The results of this testing and associated analysis provided an envelope (principally determined by melt depth) for debris coolability. However, this envelope does not encompass the full range of melt depths that are calculated for all plant accident sequences. Cooling augmentation by additional means may be needed at the late stage to assuremore » coolability for new reactor designs as well as for various accident sequences for existing reactors. In addition, the results of the CCI tests showed that lateral/axial power split is a function of concrete type. However, the first program produced limited data sets for code assessment. In light of significant differences in ablation behavior for different concrete types, additional data will be useful in reducing uncertainties and gaining confidence in code predictions. The objective of this test plan is to document the final CCI-5 test design in sufficient detail so that pretest analyses may be conducted by member organizations.« less

Authors:
 [1];  [1];  [1];  [1]
  1. Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE; Nuclear Regulatory Commission (NRC); Organization for Economic Cooperation and Development (OECD) - Nuclear Energy Agency
OSTI Identifier:
1177563
Report Number(s):
OECD/MCCI-2008-TR03
114087
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Farmer, M. T., Kilsdonk, D. J., Lomperski, S., and Aeschlimann, R. W. OECD MCCI Project 2-D Core Concrete Interaction (CCI) Tests. CCI-5 Test Plan. Rev. 1, Final. United States: N. p., 2008. Web. doi:10.2172/1177563.
Farmer, M. T., Kilsdonk, D. J., Lomperski, S., & Aeschlimann, R. W. OECD MCCI Project 2-D Core Concrete Interaction (CCI) Tests. CCI-5 Test Plan. Rev. 1, Final. United States. doi:10.2172/1177563.
Farmer, M. T., Kilsdonk, D. J., Lomperski, S., and Aeschlimann, R. W. Thu . "OECD MCCI Project 2-D Core Concrete Interaction (CCI) Tests. CCI-5 Test Plan. Rev. 1, Final". United States. doi:10.2172/1177563. https://www.osti.gov/servlets/purl/1177563.
@article{osti_1177563,
title = {OECD MCCI Project 2-D Core Concrete Interaction (CCI) Tests. CCI-5 Test Plan. Rev. 1, Final},
author = {Farmer, M. T. and Kilsdonk, D. J. and Lomperski, S. and Aeschlimann, R. W.},
abstractNote = {Ex-vessel debris coolability is an important light water reactor (LWR) safety issue. For existing plants, resolution of this issue will confirm the technical basis for severe accident management guidelines (SAMGs). For new reactors, understanding this issue will help confirm the effectiveness of the design and implementation of new accident mitigation features and severe accident management design alternatives (SAMDAs). The first OECD-MCCI program conducted reactor material experiments focused on achieving the following technical objectives: (i) provide confirmatory evidence for various cooling mechanisms through separate effect tests and data for severe accident code model development, and (ii) provide longer-term two-dimensional core-concrete interaction data for code assessment and improvement. Debris cooling mechanisms investigated as part of the first MCCI program included: (i) water ingression through cracks/fissures in the core debris, (ii) melt eruption caused by gas sparging (volcanic-type event), and (iii) large-scale crust mechanical failure leading to renewed bulk cooling. The results of this testing and associated analysis provided an envelope (principally determined by melt depth) for debris coolability. However, this envelope does not encompass the full range of melt depths that are calculated for all plant accident sequences. Cooling augmentation by additional means may be needed at the late stage to assure coolability for new reactor designs as well as for various accident sequences for existing reactors. In addition, the results of the CCI tests showed that lateral/axial power split is a function of concrete type. However, the first program produced limited data sets for code assessment. In light of significant differences in ablation behavior for different concrete types, additional data will be useful in reducing uncertainties and gaining confidence in code predictions. The objective of this test plan is to document the final CCI-5 test design in sufficient detail so that pretest analyses may be conducted by member organizations.},
doi = {10.2172/1177563},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2008},
month = {5}
}

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