Time-independent neutronic analysis of the Chernobyl accident

Journal Article · Sat Jun 01 04:00:00 EDT 1991 · Nuclear Science and Engineering; (United States)

OSTI ID:5758991

Landeyro, P A ^[1]; Buccafurni, A ^[2]

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1. ENEA, CRE Casaccia, Via Anguillarese No. 301, 00100 Rome (IT)
2. ENEA, Nuclear Safety and Health Protection, Via Brancati 48, 00144 Rome (IT)

Estimates are made of the positive reactivity introduced through the growth of the coolant void fraction in the Chernobyl reactor at both the average burnup value given by the Soviets and the maximum value. Using Monte Carlo models, various possible axial burnup distributions, displacer models, conditions in the control channels, and control rod positions are considered in calculating the insertion of positive reactivity by the manual and emergency control rods, that is, the positive scram. Two possible scenarios are examined for a second reactivity peak: (a) creation of a mixture of fuel, water, and cladding in a number of central fuel channels, resulting in the explosion of these channels, and (b) uniform vaporization throughout the entire reactor, resulting in reactor depressurization. From the data presented in this paper, it can be concluded that vaporization of the cooling water in the fuel channel gave the highest reactivity contribution to the Chernobyl accident. The positive reactivity due to insertion of the manual and emergency control rods played only a minor role in the reactivity balance of the accident.

• OSTI ID: 5758991
• Journal Information: Nuclear Science and Engineering; (United States), Journal Name: Nuclear Science and Engineering; (United States) Vol. 108:2; ISSN 0029-5639; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
COOLING SYSTEMS
EXPLOSIONS
FUEL CHANNELS
FUEL-CLADDING INTERACTIONS
HYDROGEN COMPOUNDS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
OXYGEN COMPOUNDS
RADIATION FLUX
RADIATION TRANSPORT
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
VOID FRACTION
WATER