Loading…
The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program
In this work, a detailed reevaluation of a past power-to-melt experiment performed within the so-called High Burnup Chemistry project is provided. A pressurized water reactor-type UO 2 fuel rod was base irradiated in Belgian Reactor 3 up to a peak pellet burnup of 60 MWd/kg U . After base irradiatio...
Saved in:
Published in: | Nuclear technology 2024-02, Vol.210 (2), p.216-231 |
---|---|
Main Authors: | , , , , , |
Format: | Article |
Language: | English |
Subjects: | |
Online Access: | Get full text |
Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
cited_by | |
---|---|
cites | |
container_end_page | 231 |
container_issue | 2 |
container_start_page | 216 |
container_title | Nuclear technology |
container_volume | 210 |
creator | Bonny, G. Blanpain, P. Rozzia, D. Billiet, S. Verwerft, M. Boer, B. |
description | In this work, a detailed reevaluation of a past power-to-melt experiment performed within the so-called High Burnup Chemistry project is provided. A pressurized water reactor-type UO
2
fuel rod was base irradiated in Belgian Reactor 3 up to a peak pellet burnup of 60 MWd/kg
U
. After base irradiation, the rod experienced a power ramp experiment in Belgian Reactor 2, reaching a ramp terminal level of 70 kW/m (later adjusted to 66 kW/m). Extensive post-irradiation examination was performed after both the base irradiation and the power ramp experiment. After the power ramp experiment, rod cladding failure and local fuel melting were observed. Fuel melting was observed in an 85-mm region around the peak power pellet with a normalized molten fuel radius in the range r/r
0
= 0.20 to 0.27. The threshold power for melting derived from this experiment was 63.0 ± 4.4 kW/m. |
doi_str_mv | 10.1080/00295450.2023.2264505 |
format | article |
fullrecord | <record><control><sourceid>proquest_infor</sourceid><recordid>TN_cdi_proquest_journals_2922156669</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>2922156669</sourcerecordid><originalsourceid>FETCH-LOGICAL-i240t-f9504d835bd5b963227b20b19b433ebcad499b083a1036d938c5b8a20a632a993</originalsourceid><addsrcrecordid>eNo1kE1PAjEQhhujiYj-BJMmnov93N3eVKJCgoEDHE3Tsl0o2W2xW4L8e3cDnmYmeTIz7wPAI8Ejggv8jDGVggs8opiyEaVZ14srMCCSM5TznFyDQc-gHroFd22768Y8x3wAvpdbC1dzChfhaCNKAX3ZOsH3372NrrE-wYWNVYiNLaHzMHX0xG228O0Q_WEPx1vbuDbFE5z6ZKPXyQWva7iIYRN1cw9uKl239uFSh2D18b4cT9Bs_jkdv86QoxwnVEmBeVkwYUphZMYozQ3FhkjDGbNmrUsupcEF0wSzrJSsWAtTaIp1x2op2RA8nffuY_g52DapXege7E4qKiklIsuynno5U873ifQxxLpUSZ_qEKuo_dq1ihGseqnqX6rqpaqLVPYH5dxpbg</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2922156669</pqid></control><display><type>article</type><title>The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program</title><source>Taylor and Francis Science and Technology Collection</source><creator>Bonny, G. ; Blanpain, P. ; Rozzia, D. ; Billiet, S. ; Verwerft, M. ; Boer, B.</creator><creatorcontrib>Bonny, G. ; Blanpain, P. ; Rozzia, D. ; Billiet, S. ; Verwerft, M. ; Boer, B.</creatorcontrib><description>In this work, a detailed reevaluation of a past power-to-melt experiment performed within the so-called High Burnup Chemistry project is provided. A pressurized water reactor-type UO
2
fuel rod was base irradiated in Belgian Reactor 3 up to a peak pellet burnup of 60 MWd/kg
U
. After base irradiation, the rod experienced a power ramp experiment in Belgian Reactor 2, reaching a ramp terminal level of 70 kW/m (later adjusted to 66 kW/m). Extensive post-irradiation examination was performed after both the base irradiation and the power ramp experiment. After the power ramp experiment, rod cladding failure and local fuel melting were observed. Fuel melting was observed in an 85-mm region around the peak power pellet with a normalized molten fuel radius in the range r/r
0
= 0.20 to 0.27. The threshold power for melting derived from this experiment was 63.0 ± 4.4 kW/m.</description><identifier>ISSN: 0029-5450</identifier><identifier>EISSN: 1943-7471</identifier><identifier>DOI: 10.1080/00295450.2023.2264505</identifier><language>eng</language><publisher>La Grange Park: Taylor & Francis</publisher><subject>cladding failure ; local fuel melt ; Power ramp experiment</subject><ispartof>Nuclear technology, 2024-02, Vol.210 (2), p.216-231</ispartof><rights>2023 The Author(s). Published with license by Taylor & Francis Group, LLC. 2023</rights><rights>Copyright American Nuclear Society Feb 2024</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27923,27924</link.rule.ids></links><search><creatorcontrib>Bonny, G.</creatorcontrib><creatorcontrib>Blanpain, P.</creatorcontrib><creatorcontrib>Rozzia, D.</creatorcontrib><creatorcontrib>Billiet, S.</creatorcontrib><creatorcontrib>Verwerft, M.</creatorcontrib><creatorcontrib>Boer, B.</creatorcontrib><title>The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program</title><title>Nuclear technology</title><description>In this work, a detailed reevaluation of a past power-to-melt experiment performed within the so-called High Burnup Chemistry project is provided. A pressurized water reactor-type UO
2
fuel rod was base irradiated in Belgian Reactor 3 up to a peak pellet burnup of 60 MWd/kg
U
. After base irradiation, the rod experienced a power ramp experiment in Belgian Reactor 2, reaching a ramp terminal level of 70 kW/m (later adjusted to 66 kW/m). Extensive post-irradiation examination was performed after both the base irradiation and the power ramp experiment. After the power ramp experiment, rod cladding failure and local fuel melting were observed. Fuel melting was observed in an 85-mm region around the peak power pellet with a normalized molten fuel radius in the range r/r
0
= 0.20 to 0.27. The threshold power for melting derived from this experiment was 63.0 ± 4.4 kW/m.</description><subject>cladding failure</subject><subject>local fuel melt</subject><subject>Power ramp experiment</subject><issn>0029-5450</issn><issn>1943-7471</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2024</creationdate><recordtype>article</recordtype><sourceid>0YH</sourceid><recordid>eNo1kE1PAjEQhhujiYj-BJMmnov93N3eVKJCgoEDHE3Tsl0o2W2xW4L8e3cDnmYmeTIz7wPAI8Ejggv8jDGVggs8opiyEaVZ14srMCCSM5TznFyDQc-gHroFd22768Y8x3wAvpdbC1dzChfhaCNKAX3ZOsH3372NrrE-wYWNVYiNLaHzMHX0xG228O0Q_WEPx1vbuDbFE5z6ZKPXyQWva7iIYRN1cw9uKl239uFSh2D18b4cT9Bs_jkdv86QoxwnVEmBeVkwYUphZMYozQ3FhkjDGbNmrUsupcEF0wSzrJSsWAtTaIp1x2op2RA8nffuY_g52DapXege7E4qKiklIsuynno5U873ifQxxLpUSZ_qEKuo_dq1ihGseqnqX6rqpaqLVPYH5dxpbg</recordid><startdate>20240201</startdate><enddate>20240201</enddate><creator>Bonny, G.</creator><creator>Blanpain, P.</creator><creator>Rozzia, D.</creator><creator>Billiet, S.</creator><creator>Verwerft, M.</creator><creator>Boer, B.</creator><general>Taylor & Francis</general><general>American Nuclear Society</general><scope>0YH</scope></search><sort><creationdate>20240201</creationdate><title>The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program</title><author>Bonny, G. ; Blanpain, P. ; Rozzia, D. ; Billiet, S. ; Verwerft, M. ; Boer, B.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-i240t-f9504d835bd5b963227b20b19b433ebcad499b083a1036d938c5b8a20a632a993</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2024</creationdate><topic>cladding failure</topic><topic>local fuel melt</topic><topic>Power ramp experiment</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Bonny, G.</creatorcontrib><creatorcontrib>Blanpain, P.</creatorcontrib><creatorcontrib>Rozzia, D.</creatorcontrib><creatorcontrib>Billiet, S.</creatorcontrib><creatorcontrib>Verwerft, M.</creatorcontrib><creatorcontrib>Boer, B.</creatorcontrib><collection>Taylor & Francis_OA刊</collection><jtitle>Nuclear technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Bonny, G.</au><au>Blanpain, P.</au><au>Rozzia, D.</au><au>Billiet, S.</au><au>Verwerft, M.</au><au>Boer, B.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program</atitle><jtitle>Nuclear technology</jtitle><date>2024-02-01</date><risdate>2024</risdate><volume>210</volume><issue>2</issue><spage>216</spage><epage>231</epage><pages>216-231</pages><issn>0029-5450</issn><eissn>1943-7471</eissn><abstract>In this work, a detailed reevaluation of a past power-to-melt experiment performed within the so-called High Burnup Chemistry project is provided. A pressurized water reactor-type UO
2
fuel rod was base irradiated in Belgian Reactor 3 up to a peak pellet burnup of 60 MWd/kg
U
. After base irradiation, the rod experienced a power ramp experiment in Belgian Reactor 2, reaching a ramp terminal level of 70 kW/m (later adjusted to 66 kW/m). Extensive post-irradiation examination was performed after both the base irradiation and the power ramp experiment. After the power ramp experiment, rod cladding failure and local fuel melting were observed. Fuel melting was observed in an 85-mm region around the peak power pellet with a normalized molten fuel radius in the range r/r
0
= 0.20 to 0.27. The threshold power for melting derived from this experiment was 63.0 ± 4.4 kW/m.</abstract><cop>La Grange Park</cop><pub>Taylor & Francis</pub><doi>10.1080/00295450.2023.2264505</doi><tpages>16</tpages><oa>free_for_read</oa></addata></record> |
fulltext | fulltext |
identifier | ISSN: 0029-5450 |
ispartof | Nuclear technology, 2024-02, Vol.210 (2), p.216-231 |
issn | 0029-5450 1943-7471 |
language | eng |
recordid | cdi_proquest_journals_2922156669 |
source | Taylor and Francis Science and Technology Collection |
subjects | cladding failure local fuel melt Power ramp experiment |
title | The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program |
url | http://sfxeu10.hosted.exlibrisgroup.com/loughborough?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-08T12%3A50%3A22IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_infor&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=The%20UO2%20Power-to-Melt%20Experiment%20Performed%20in%20the%20High%20Burnup%20Chemistry%20International%20Program&rft.jtitle=Nuclear%20technology&rft.au=Bonny,%20G.&rft.date=2024-02-01&rft.volume=210&rft.issue=2&rft.spage=216&rft.epage=231&rft.pages=216-231&rft.issn=0029-5450&rft.eissn=1943-7471&rft_id=info:doi/10.1080/00295450.2023.2264505&rft_dat=%3Cproquest_infor%3E2922156669%3C/proquest_infor%3E%3Cgrp_id%3Ecdi_FETCH-LOGICAL-i240t-f9504d835bd5b963227b20b19b433ebcad499b083a1036d938c5b8a20a632a993%3C/grp_id%3E%3Coa%3E%3C/oa%3E%3Curl%3E%3C/url%3E&rft_id=info:oai/&rft_pqid=2922156669&rft_id=info:pmid/&rfr_iscdi=true |