General Synthesis Report of the Different ADS Design Status. Establishment of a Catalogue of the R&D needs

This document is a General Synthesis Report of the Different ADS Design Status being designed within the EUROTRANS Integrated Project; an FP6 European commission partially funded programme. This project had the goal to demonstrate the possibility of nuclear waste transmutation/burning in Accelerator Driven Systems (ADS) at industrial scale.The focus is on a Pb-cooled ADS for the European Facility on Industrial scale Transmuter (ETD/EFIT) with a back-up solution based on an He cooled ADS.As an intermediate step towards this industrial-scale prototype, an eXperimental Transmuter based on ADS concept (ETD/XT-ADS) able to demonstrate both the feasibility of the ADS concept and to accumulate experience when using dedicated fuel sub-assemblies or dedicated pins within a MOX fuel core has been also studied.The two machines (XT-ADS and Pb cooled EFIT) have been designed in a consistent way bringing more credibility to the potential licensing of these plants and with sufficient details to allow definition of the critical issues as regards design, safety and associated technological and basic R&D needs. The different designs fit rather well with the technical objectives fixed at the beginning of the project in consistency with the European Roadmap on ADS development.For what concerns the accelerator, the superconducting LINAC has been clearly assessed as the most suitable concept for the three reactors in particular with respect to the stringent requirements on reliability. Associated R&D needs have been identified and will be focused on critical components (injector, cryomodule) long term testing.The design of the different ADS has been performed in view of what is reasonably achievable pending the completion of R&D programmes. The way the EUROTRANS Integrated Project has been organised with other domains than the DM1 Design being specifically devoted to R&D tasks in support to the overall ETD/EFIT and ETD/XT-ADS design tasks has been helpful. The other domains were centred on the assessment of reactivity measurement techniques (DM2 ECATS), on the development of U-free dedicated fuels (DM3 AFTRA), on materials behaviour and heavy liquid metal technology (DM4 DEMETRA) and on nuclear data assessment (DM5 NUDATRA). Pending questions associated to technology gaps have been identified through the different appropriate R&D work programmes and a Catalogue of the R&D needs has been established.Finally, the work within the EUROTRANS integrated project has provided an overall assessment of the feasibility at a reasonable cost for an ADS based transmutation so that a decision can be taken to launch a detailed design and construction of the intermediate step Experimental ADS now already launched within the 7th FP programme under the name of Common Design Team (CDT)

Natural Circulation Limits achievable in a PWR

The present paper deals with the Natural Circulation (NC) phenomenon in Pressurized Water nuclear Reactors (PWR). In the first part, data gathered from relevant experiments in PWR simulators are considered. These allowed the establishment of a flow map that has been used for evaluating the NC performance of various reactor concepts. In the second part, a theoretical study has been completed to assess the power removal capability by NC from the core of a PWR having the current geometric configuration. Taking as reference a PWR equipped with U-tubes steam generators, two-phase conditions occur in the core at power levels less than 20% nominal power. Therefore, for core power larger than this value the reactor cannot be classified any more as a PWR. The study shows that from a thermohydraulic point of view, the core can operate at power levels close to the current nominal value without experiencing thermal crisis. Limited consideration has been given to the neutronic design of the core

RELAP5/MOD.2 Post Test Analysis and Accuracy Quantification of Lobi Test BL-34

The present document deals with the Relap5/Mod3.2 analysis of the small break LOCA experiment BL-34 performed in LOBI/MOD2 facility. LOBI/MOD2 was a PWR simulator (Integral Test Facility) installed at JRC (Joint Research Center) in Ispra Establishment (1). Volume scaling and core power scaling factors are 1/712, with respect to the KWU Siemens 1300 MWe (3900 MWt) standard reactor. The experiment is originated by a small break in the cold leg (2" equivalent break area in the plant) without the actuation of the high pressure injection system. Low pressure injection system actuation occurs after core dry-out and accumulators intervention is foreseen when primary pressure falls below 4 MPa. The Relap5 code has been extensively used at University of Pisa; the nodalization of LOBI facility has been qualified through the application of the version Relap5/Mod2 to the same experiment and another test performed in the same facility. Sensitivity analyses have been addressed to the influence of several parameters (like discharge break coefficient, time of accumulators start etc.) upon the predicted transient evolution. Qualitative and quantitative code calculation accuracy evaluation has been performed

US NRC NUREG - RELAP5/MOD3.2 Post Test Analysis and Accuracy Quantification of SPES Test SP-SB-03

The present document deals with the Relap5/Mod3.2 analysis of the Small Break LOCA experiment SP-SB-03 performed in SPES facility. SPES is a PWR simulator (Integral Test Facility) installed at SIET center in Piacenza (I). Volume scaling and core power scaling factors are 1/427, with respect to the Westinghouse 900 MWe standard reactor. The experiment is originated by a small break in the cold leg (2" equivalent break area in the plant) without the actuation of the high pressure injection system. Low pressure injection system actuation occurs after core dry-out. The Relap5 code has been extensively used at University of Pisa; the nodalization of SPES facility has been qualified through the application of the version Relap5/Mod2 to the same experiment and another test performed in the same facility. Sensitivity analyses have been addressed to the influence of several parameters (like discharge break coefficient, time of accumulators start etc.) upon the predicted transient evolution. Qualitative and quantitative code calculation accuracy evaluation has been performed

RELAP5/MOD3 .2 Post Test Analysis and Accuracy Quantification of SPES Test SP-SB-04

The present document deals with the Relap5fMod3.2 analysis of the small br.!ak LOCA experiment SP-SB-04 performed in SPES facility. SPES is a PWR simulator (integral Test Facility) installed at SIET center in Pia::enza (IT). Volume scaling and core power scaling factors are 1/427, with respect to the Westinghouse 900 MWe standard reactor. The experiment is originated by a small break in the cold leg (2»> equivalent break area in the plant) without the actuation of the high pressure injection system. The test starts from full power and is the counterpart of the test SP-SB-03, that started at an initial power roughly equal to 10% of nominal power. Low pressure injection system actuation occurs after core dry-out. The Relap5 code has been extensively used at University of Pisa; the nodalizatic'n of SPES facility has, been qualified through the application of the version Relap5/Mod2 to the same experiment and another test performed in the same facility. Sensitivity analyses have been addressed to the influence of several parameters (like discharge break coefficient, time of accumulators start etc.) upon the predicted transient evolution. Qualitative and quantitative code calculation accuracy evaluation has been performed.