Transport-diffusion comparisons for small core LMFBR disruptive accidents
A number of numerical experiments were performed to assess the validity of diffusion theory for calculating the reactivity state of various small core LMFBR disrupted geometries. The disrupted configurations correspond, in general, to various configurations predicted by SAS3A for transient undercooling (TUC) and transient overpower (TOP) accidents for homogeneous cores and to the ZPPR-7 configurations for heterogeneous core. In all TUC cases diffusion theory was shown to be inadequate for the calculation of reactivity changes during core disassembly.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5167406
- Report Number(s):
- ORNL/CSD/TM-38
- Country of Publication:
- United States
- Language:
- English
Similar Records
Neutronic analysis of LMFBRs during severe core disruptive accidents
Comparison of SAS3A and MELT-III predictions for a transient overpower hypothetical accident
Multiphase transients with coolant and core materials in LMFBR core disruptive accident energetics evaluations
Technical Report
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6494159
Comparison of SAS3A and MELT-III predictions for a transient overpower hypothetical accident
Conference
·
Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:7334754
Multiphase transients with coolant and core materials in LMFBR core disruptive accident energetics evaluations
Technical Report
·
Thu Jun 01 00:00:00 EDT 1978
·
OSTI ID:6938664
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
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
REACTIVITY
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
TRANSPORT THEORY
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
REACTIVITY
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
TRANSPORT THEORY