Title: Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations

Journal Article · · Progress in Nuclear Energy
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Not Available

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC05-00OR22725; AC05-76RL01830
OSTI ID:
1832608
Report Number(s):
PNNL-SA--164959; S014919702100398X; 104042; PII: S014919702100398X
Journal Information:
Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Journal Issue: C Vol. 143; ISSN 0149-1970
Publisher:
ElsevierCopyright Statement
Country of Publication:
United Kingdom
Language:
English

References (9)

Sensitivity analysis for best-estimate thermal models of vertical dry cask storage systems journal August 2017
Shielding Analysis Capability of UNF-ST&DARDS journal September 2017
Development of Streamlined Nuclear Safety Analysis Tool for Spent Nuclear Fuel Applications journal September 2017
Thermal Analysis Capability of UNF-ST&DARDS journal September 2017
Containment Analysis Capability of UNF-ST&DARDS journal September 2017
As-Loaded Criticality Margin Assessment of Dual-Purpose Canisters Using UNF-ST&DARDS journal September 2017
Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE journal May 2011
Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks journal August 2016
Reactor Physics Methods and Analysis Capabilities in SCALE journal May 2011

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
LWR
UNF-ST&DARDS
decay heat
spent nuclear fuel