Nuclear Criticality Safety Tools in the Chernobyl-4 Accident Analysis
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5559806
The collaboration with the Italian Safety Authority (DISP), started in July 1986, has the aim of studying, from a neutronic point of view, the possible initiator event and the accident dynamics in unit four of the Chernobyl nuclear power plant. This report was produced within the framework of that collaboration. A main condition of the present work was making use of standard calculational methods employed in nuclear criticality safety analysis. This means that the neutron multiplication factor calculation should be made with the modules and the cross-section libraries of the SCALE system or in any case with some KENO IV version and the burnup calculation with the ORIGEN code.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5559806
- Report Number(s):
- CONF-880601-; CODEN: TANSA; TRN: 89-027140
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 56; Conference: American Nuclear Society Annual Meeting , San Diego, CA (United States), 12-16 Jun 1988; ISSN 0003-018X
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
97 MATHEMATICS AND COMPUTING
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
CHERNOBYLSK-4 REACTOR
REACTOR ACCIDENTS
REACTOR PHYSICS
BURNUP
COMPUTERIZED SIMULATION
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K CODES
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O CODES
REACTIVITY
REACTOR CORES
S CODES
SCRAM
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GRAPHITE MODERATED REACTORS
LWGR TYPE REACTORS
PHYSICS
POWER REACTORS
REACTOR COMPONENTS
REACTOR SHUTDOWN
REACTORS
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SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
Nuclear Criticality Safety Program (NCSP)
Italian Safety Authority (DISP): Chernobyl Nuclear Power Plant Unit 4
SCALE System
KENO IV
ORIGEN Code
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
97 MATHEMATICS AND COMPUTING
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
CHERNOBYLSK-4 REACTOR
REACTOR ACCIDENTS
REACTOR PHYSICS
BURNUP
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
CROSS SECTIONS
K CODES
MULTIPLICATION FACTORS
O CODES
REACTIVITY
REACTOR CORES
S CODES
SCRAM
ACCIDENTS
COMPUTER CODES
ENRICHED URANIUM REACTORS
GRAPHITE MODERATED REACTORS
LWGR TYPE REACTORS
PHYSICS
POWER REACTORS
REACTOR COMPONENTS
REACTOR SHUTDOWN
REACTORS
SHUTDOWN
SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
Nuclear Criticality Safety Program (NCSP)
Italian Safety Authority (DISP): Chernobyl Nuclear Power Plant Unit 4
SCALE System
KENO IV
ORIGEN Code
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated