Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test
The Power Burst Facility (PBF) was designed to provide experimental data to determine the thresholds for failure during accident conditions. Thus, the PBF benchmark using severe accidental analysis codes is essential to designing reactor for current directions. This assessment verified and validated...
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| Format: | Article |
| Language: | English |
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Wiley
2017-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2017/7456380 |
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| author | Noppawan Rattanadecho Somboon Rassame Kampanart Silva Chris Allison Judith Hohorst |
| author_facet | Noppawan Rattanadecho Somboon Rassame Kampanart Silva Chris Allison Judith Hohorst |
| author_sort | Noppawan Rattanadecho |
| collection | DOAJ |
| description | The Power Burst Facility (PBF) was designed to provide experimental data to determine the thresholds for failure during accident conditions. Thus, the PBF benchmark using severe accidental analysis codes is essential to designing reactor for current directions. This assessment verified and validated that the RELAP/SCDAPSIM/MOD3.4 code can be used to assess the Severe Fuel Damage Scoping Test (SFD-ST) performed in the PBF facility. This study compares the cladding temperatures and hydrogen production results calculated by the RELAP/SCDAPSIM/MOD3.4 code with experimental data and calculated results from the SCDAP/RELAP5/MOD3.2 and SCDAP/RELAP5/MOD3.3 codes. The interested parameters are cladding temperature and hydrogen production since the cladding temperature affects hydrogen production and consequently influences the accident scenario. The calculated cladding temperatures and hydrogen production results from the RELAP/SCDAPSIM/MOD3.4 code are in a good agreement with the experimental data and are generally more reasonable than the calculated results from the SCDAP/RELAP5/MOD3.2 and SCDAP/RELAP5/MOD3.3 codes. There are some discrepancies in the cladding temperature and hydrogen production results but they are expected. |
| format | Article |
| id | doaj-art-a400b693d5804d02bccbb9b34014d5ef |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2017-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-a400b693d5804d02bccbb9b34014d5ef2025-02-03T01:30:40ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/74563807456380Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping TestNoppawan Rattanadecho0Somboon Rassame1Kampanart Silva2Chris Allison3Judith Hohorst4Department of Nuclear Engineering, Chulalongkorn University, 254 Phayathai Rd, Pathumwan, Bangkok 10330, ThailandDepartment of Nuclear Engineering, Chulalongkorn University, 254 Phayathai Rd, Pathumwan, Bangkok 10330, ThailandThailand Institute of Nuclear Technology (Public Organization), 9/9 Moo 7, Saimoon, Ongkharak, Nakorn Nayok 26120, ThailandInnovation Systems Software, 2585 Briar Creek Ln., Ammon, Idaho 83406, USAInnovation Systems Software, 2585 Briar Creek Ln., Ammon, Idaho 83406, USAThe Power Burst Facility (PBF) was designed to provide experimental data to determine the thresholds for failure during accident conditions. Thus, the PBF benchmark using severe accidental analysis codes is essential to designing reactor for current directions. This assessment verified and validated that the RELAP/SCDAPSIM/MOD3.4 code can be used to assess the Severe Fuel Damage Scoping Test (SFD-ST) performed in the PBF facility. This study compares the cladding temperatures and hydrogen production results calculated by the RELAP/SCDAPSIM/MOD3.4 code with experimental data and calculated results from the SCDAP/RELAP5/MOD3.2 and SCDAP/RELAP5/MOD3.3 codes. The interested parameters are cladding temperature and hydrogen production since the cladding temperature affects hydrogen production and consequently influences the accident scenario. The calculated cladding temperatures and hydrogen production results from the RELAP/SCDAPSIM/MOD3.4 code are in a good agreement with the experimental data and are generally more reasonable than the calculated results from the SCDAP/RELAP5/MOD3.2 and SCDAP/RELAP5/MOD3.3 codes. There are some discrepancies in the cladding temperature and hydrogen production results but they are expected.http://dx.doi.org/10.1155/2017/7456380 |
| spellingShingle | Noppawan Rattanadecho Somboon Rassame Kampanart Silva Chris Allison Judith Hohorst Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test Science and Technology of Nuclear Installations |
| title | Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test |
| title_full | Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test |
| title_fullStr | Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test |
| title_full_unstemmed | Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test |
| title_short | Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test |
| title_sort | assessment of relap scdapsim mod3 4 prediction capability with severe fuel damage scoping test |
| url | http://dx.doi.org/10.1155/2017/7456380 |
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