Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test-Reference-Cited by-同舟云学术

Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test

Published:2017 Issue: Volume:2017 Page:1-12
ISSN:1687-6075
Container-title:Science and Technology of Nuclear Installations
language:en
Short-container-title:Science and Technology of Nuclear Installations

Author:

Rattanadecho Noppawan¹^ORCID,Rassame Somboon¹^ORCID,Silva Kampanart²,Allison Chris³,Hohorst Judith³^ORCID

Affiliation:

1. Department of Nuclear Engineering, Chulalongkorn University, 254 Phayathai Rd, Pathumwan, Bangkok 10330, Thailand

2. Thailand Institute of Nuclear Technology (Public Organization), 9/9 Moo 7, Saimoon, Ongkharak, Nakorn Nayok 26120, Thailand

3. Innovation Systems Software, 2585 Briar Creek Ln., Ammon, Idaho 83406, USA

Abstract

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.

Funder

Chulalongkorn University

Publisher

Hindawi Limited

Subject

Nuclear Energy and Engineering

Link

http://downloads.hindawi.com/journals/stni/2017/7456380.pdf

Reference11 articles.

1. An assessment of effectiveness of core exit temperatures with respect to PWR core damage state using RELAP/SCDAPSIM/MOD3.4

2. Development and testing of RBMK-1500 model for BDBA analysis employing RELAP/SCDAPSIM code

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