Nuclear Fuel Safety Criteria Technical Review [electronic resource] /
Organisation for Economic Co-operation and Development.
Nuclear Energy Agency.
Paris : OECD Publishing,
2001.
Nuclear reactor safety is primarily concerned with the prevention of radiation-related damage to the public from the operation of commercial nuclear reactors; safety limits are introduced to avoid fuel failures during normal operation, or to mitigate the consequences of reactor accidents in which substantial damage is done to the reactor core. In this report, brief descriptions of 20 fuel-related safety criteria are presented along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them. No attempt was made to categorise the criteria according to event type or risk significance.
Description based upon print version of record.
FOREWORD; CONTENTS; EXECUTIVE SUMMARY; 1. INTRODUCTION; 2. TASK FORCE OUTLINE; 2.1 Fuel safety criteria: historical perspective, background of task force; 2.2 "New" elements related to fuel design and operation; 2.3 Task force approach to assessing the potential effects of new elements; 3 REVIEW OF SAFETY CRITERIA; 3.1 CPR/DNBR; 3.2 Reactivity coefficient; 3.3 Shutdown margin; 3.4 Enrichment; 3.5 Crud deposition; 3.6 Strain level; 3.7 Oxidation and hydriding; 3.8 Internal gas pressure; 3.9 Thermal mechanical loads (PCMI); 3.10 Pellet cladding interaction (PCI); 3.11 Fuel fragmentation (RIA)
3.12 Fuel failure (RIA)3.13 Cladding embrittlement/PCT (non-LOCA run away oxidation); 3.14 Cladding embrittlement/oxidation (LOCA); 3.15 Blowdown/seismic loads; 3.16 Assembly holddown force; 3.17 Coolant activity; 3.18 Gap activity; 3.19 Source term; 4. ASSESSMENT OF ANALYSIS METHODS; 4.1 Steady-state fuel rod codes; 4.2 Transient fuel rod codes; 4.3 Reactor kinetics codes; 4.4 Reactor static codes; 4.5 Thermal-hydraulic codes; 4.6 Subchannel codes; 4.7 Reactor core structural analysis codes; 5. SPECIAL TOPICS; 5.1 High burnup; 5.2 Core management; 5.3 MOX; 5.4 Mixed cores
5.5 Incomplete control rod insertion5.6 Axial offset anomaly; 6. TEST PROGRAMMES; 6.1 ANL test programme; 6.2 Halden reactor project (HRP); 6.3 Belgonucleaire R&D programme; 6.4 CABRI; 6.5 TAGCIS/TAGCIR/HYDRAZIR; 6.6 CINOG; 6.7 EDGAR; 6.8 NSRR; 7. RECOMMENDATIONS AND SUMMARY; 7.1 CPR/DNBR; 7.2 Reactivity coefficients; 7.3 Shutdown margin; 7.4 Enrichment; 7.5 Crud deposition; 7.6 Strain level; 7.7 Oxidation and hydriding; 7.8 Internal gas pressure; 7.9 Thermal-mechanical loads (PCMI); 7.10 Thermal-mechanical operating limit; 7.11 PCI; 7.12 RIA - fuel fragmentation and fuel failure
7.13 Cladding embrittlement/oxidation7.14 Blowdown/seismic loads; 7.15 Assembly holddown force; 7.16 Coolant activity; 7.17 Gap activity; 7.18 Source term; 7.19 Analysis methods; 7.20 High burnup fuel programmes; 7.21 Conclusion; 8. ACKNOWLEDGEMENT OF TASK FORCE PARTICIPANTSAND REPORT CONTENT; 9. GLOSSARY; REFERENCES
Nuclear reactor safety is primarily concerned with the prevention of radiation-related damage to the public from the operation of commercial nuclear reactors; safety limits are introduced to avoid fuel failures during normal operation, or to mitigate the consequences of reactor accidents in which substantial damage is done to the reactor core. In this report, brief descriptions of 20 fuel-related safety criteria are presented along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them. No attempt was made to categorise the criteria according to event type or risk significance.
Nuclear energy.
Nuclear fuels -- Safety measures.
Nuclear fuels.
Nuclear power.
Nuclear fuels
Mechanical Engineering
Engineering & Applied Sciences
Nuclear Engineering