Sicherheitsstudie für HTR-Konzepte unter deutschen Standortbedingungen Hauptband zur Phase IB
Sicherheitsstudie für HTR-Konzepte unter deutschen Standortbedingungen Hauptband zur Phase IB
The probabilistic safety study of the HTR concept has provided a comprehensive perspective of the possible accidents to HTR's, as exemplified by the HTR-1160. It confirms the previous understanding of the safety characteristics of this type of reactor which are based essentially on the use of r...
Saved in:
Personal Name(s): | Kröger, W. (Editor) |
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Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
Imprint: |
Jülich
Kernforschungsanlage Jülich GmbH Zentralbibliothek, Verlag
1981
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Physical Description: |
getr. Pag. |
Document Type: |
Report Book |
Research Program: |
ohne Topic |
Series Title: |
Spezielle Berichte der Kernforschungsanlage Jülich
0136,01 |
Link: |
OpenAccess OpenAccess |
Publikationsportal JuSER |
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520 | |a The probabilistic safety study of the HTR concept has provided a comprehensive perspective of the possible accidents to HTR's, as exemplified by the HTR-1160. It confirms the previous understanding of the safety characteristics of this type of reactor which are based essentially on the use of refractory materials for the core structure, the large and invariant thermal capacity, the use of an inert gas as the coolant and the large margins between operating and failure temperatures.Within the spectrum of accidents, core heat-up, caused by failure of the power supplies to the reactor or by interruption of the cooling system, is of major significance. This accident causes no serious effects to the environment if the reactor containment building remains intact; however, in certain infrequent events the containment building could fail due to overpressure after about one week at the earliest and a significant environmental hazard would ensue. The other accidents - depressurisation, water and air ingress - are by comparison of distinctly lower importance to the overall risk. A common feature of all the significant accidents is that within the first five hours the maximum release of radioactivity to the reactor containment building is the inventory of the primary circuit, while the fission product inventory of the core is securely retained. The accidents investigated are characterised in the study by the probability of occurrence, by the types and quantities of the fission products released and by the period of release. It was stipulated that in this phase of the study the health risk to the neighbouring population should not be determined. However, the estimated quantities of released nuclides and their associated time of release lead to the conclusion that the worst possible damage to the environment is very limited. This arises from the inherent safety characteristics of the HTR and the comparatively long period available for counter measures.This risk can be even further reduced if a few minor changes to the plant design, identified in this study, were to be adopted. | ||
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