SAS4A validation and analysis of inpile experiments for slow ramp TOP's. [LMFBR]
Conference
·
OSTI ID:5986478
In the licensing process for an LMFBR, the margins for safety are determined by considering many accident sequences that are within the design basis for the plant. However, to establish the safety margin beyond the design basis, also considered are accidents that have an extremely low probability of occurrence but the potential for significant consequences - such as hypothetical core-disruptive accidents (HCDAs). Assessments of the potential for HCDAs that would severely disrupt the reactor system and release radioactive material to the reactor containment (and possibly to the atmosphere) rely heavily on large-scale integrated computer codes such as SAS. The latest version of the SAS LMFBR accident analysis code, SAS4A, has recently been completed and released. One important activity which has been a part of SAS development is code validation for which a comprehensive plan has been formulated. Analysis of In Pile Experiments, mainly TREAT, form a large part of this.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5986478
- Report Number(s):
- CONF-850410-22; ON: DE85004821
- Country of Publication:
- United States
- Language:
- English
Similar Records
SAS4A LMFBR whole core accident analysis code
SAS4A: A computer model for the analysis of hypothetical core disruptive accidents in liquid metal reactors
Simulating unprotected accidents for advanced liquid metal reactors using the SAS4A accident analysis code
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5986469
SAS4A: A computer model for the analysis of hypothetical core disruptive accidents in liquid metal reactors
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6434146
Simulating unprotected accidents for advanced liquid metal reactors using the SAS4A accident analysis code
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:5011228
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
REACTIVITY WORTHS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENT OVERPOWER ACCIDENTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
REACTIVITY WORTHS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENT OVERPOWER ACCIDENTS