Document: NUREG-0800
Document ID: fdfad241-da82-4ccf-9803-085cbf8ad29e
Document Type: srp
Title: - 15.3.4-12
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
izure event and total loss-of-flow event.) 18. COAST (SSAR; CENPD-98). (Calculates the time-dependent reactor coolant mass flow rate in each loop during reactor coolant pump coastdown transients.) 19. STRIKIN-II (CENPD-133; CENPD-135 Supps. 2 and 4). (Calculates the cladding and fuel temperatures for an average or hot fuel rod.) 20 NUREG-1465, "Accident Source Terms for Light-Water Nuclear Power Plants," February 1995.