The objectives of the proposal are to evaluate the impact of SAM strategies on radiological behaviour and the optimisation of their implementation to minimise any adverse radiological effects. To establish a comprehensive technical basis for the definition of source terms for operating reactors across Europe, and subsequent definition of realistic source terms for operating reactors, with provision made for implementation of SAM measures. This proposal is based on a broad spectrum of analysis involving 9 reactor designs (12 reference plants), representative of the operating reactors in both current and prospective member states. Evaluation of the results would include the impact of SAM measures on accident progression, plant status and radiological releases; recommendations on the optimisation of SAM implementation; and definition of representative source terms.
1.Evaluation of the potential impact of SAM strategies on both the accident progression and the radiological behaviour and, where possible, recommendations on the potential for the optimisation of their implementation;
2.A comprehensive technical basis has been established, from the results of both OPTSAM and the previous STU study, for the determination of potential source terms for operating reactors across Europe;
3.A reasonably bounding set of potential early releases into the environment (in the first 1 - 2 days) for operating reactors, with provision made for the implementation of SAM measures, has been proposed.
This study has the following objectives:
1.To evaluate the impact of SAM strategies on the radiological behaviour and to examine the potential for the optimisation of their implementation to minimise any adverse radiological effects.
2.To establish a comprehensive technical basis for the definition of source terms for operating reactors across Europe.
3.To define a set of realistic source terms for operating reactors, with provision made for the implementation of SAM measures and to compare them with the existing source term definitions.
This study is based on a broad spectrum of analysis involving 9 reactor designs that are regarded as representative of the reactors operating in both current and prospective member states of the European Union. The scope is summarised as follows:
WP1: The key core damage accident sequences, for the 11 reference plants, would be identified and described. In addition to the accident sequences more usually involving releases into the primary containment, emphasis is also placed on containment bypass sequences.
WP2: The key issues to be addressed in the sensitivity analysis would be identified and defined. This would be in two parts:
-Review of information: This would identify the major issues, both in terms of the impact on plant status and the associated radiological releases.
-Definition of the sensitivity study matrix.
WP3: For each of the key sequences baseline source terms would be defined, calculated predominantly using integrated severe accident analysis codes. For each sensitivity study, the predictions would be evaluated against the baseline values to assess the impact of the SAM strategies on either the plant status or radiological releases. Issues concerning the operational and design aspects would be examined.
WP4: The key findings of WP3 would be discussed and evaluated. This would be conducted in two ways: in the context of risk reduction potential and recommendations on their optimal implementation and operation.
Finally, an outline methodology would be developed to determine representative source terms for operating reactors; as, for example, would be required as input to a Level 3 PSA.
Funding SchemeCSC - Cost-sharing contracts
250 68 Rez - Praha
162 16 Stockholm
205 09 Malmoe