Nuclear Fuel Safety Criteria Technical Review
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 su...
| Autor principal: | |
|---|---|
| Autores Corporativos: | , |
| Formato: | Libro electrónico |
| Idioma: | Inglés |
| Publicado: |
Paris :
OECD Publishing
2001.
|
| Colección: | Nuclear safety Nuclear fuel safety criteria
|
| Materias: | |
| Ver en Biblioteca Universitat Ramon Llull: | https://discovery.url.edu/permalink/34CSUC_URL/1im36ta/alma991009705100806719 |
Tabla de Contenidos:
- 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
