Published September 1975 | Version v1
Report Restricted

Analysis of Loss of Flow accidents for the SNR-300 Mark-Ia core

Creators

Description

This report summarizes the important results from the LOF HCDA simulations without scram for the fresh Mark-Ia core of SNR-300, which were carried out with the CAPRI-2/KADIS code systems for given pump coast down characteristics. The code systems and important parameters of the Mark-Ia core are first briefly described. The main part discusses the simulated accident sequence for the defined base case and the influence of important model parameters. Also the results for the limiting mild and energetic LOF cases are presented, which were defined by a combined variation of model parameters

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Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
42 p.
Report number
KFK-INR--1223/1

INIS

Country of Publication
Germany
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
37002656
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ACCIDENTS; COMPUTER CODES; LOSS OF FLOW; SAFETY ANALYSIS; SNR REACTOR; SODIUM COOLED REACTORS
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SODIUM COOLED REACTORS

Optional Information

Notes
Refs, figs, tabs
Secondary number(s)
INIS-DE-KFK--019