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Let S be a deeply embedded, equicharacteristic, Artinian Gorenstein local ring. We prove that if R is a non-Gorenstein quotient of S of small colength, then every totally reflexive R -module is free. Indeed, the second syzygy of the canonical module of R has a direct summand T which is a test module for freeness over R in the sense that if Tor + R (T , N) = 0 , for some finitely generated R -module N , then N is free. [ABSTRACT FROM AUTHOR]

A conceptual design of Advanced Fusion Neutron Source, A-FNS, has been conducted to achieve early realization of fusion-like neutron irradiation test for fusion reactor materials in Japan. A-FNS provides eight test modules to obtain irradiation data for fusion reactor materials. Conceptual design activities on Blanket Functional Materials Test Module (BFMTM), Tritium Release Test Module (TRTM) and Activated Corrosion Products Module (ACPM) were described among the A-FNS test modules. Also, basic concepts of the sub-system cells for the TRTM and the ACPM were also discussed.

The test facility (TF) is one of the three major facilities of the International Fusion Material Irradiation Facility (IFMIF). Engineering designs of TF main systems and key components have been initiated and developed in the IFMIF EVEDA (Engineering Validation and Engineering Design Activities) phase since 2007. The related work covers the designs of a test cell which is the meeting point of the TF and accelerator facility and lithium facility, a series of test modules for experiments under different irradiation conditions, an access cell to accommodate remote handling systems, four test module handling cells for test module processing and assembling, and test facility ancillary systems for engineering support on energy, media, and control infrastructure. This paper summarizes the principle functions, brief specifications, and the current design status of the above mentioned IFMIF TF systems and key components. [ABSTRACT FROM AUTHOR]

A ring with a test module of finite upper complete intersection dimension is complete intersection. [ABSTRACT FROM AUTHOR]

Abstract: Under Broader Approach (BA) Agreement between EURATOM and Japan, IFMIF/EVEDA (International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities) has been performed since the middle of 2007. IFMIF presents three main facilities (the Accelerator Facility, Li Target Facility and Test Facilities). A previous design of IFMIF was summarized in the comprehensive design report [1]. The present EVEDA phase aims at producing a detailed, complete and fully integrated engineering design of IFMIF. The delivery of the “Intermediate IFMIF Engineering Design Report” is foreseen mid-2013. The goal of IFMIF is to obtain the indispensable design database to allow the design and licensing of DEMO and ensuring commercial reactors thanks to the materials data set obtained from planned evaluation tests such irradiations in high flux test modules (HFTM-vertical rig, HFTM-horizontal rig), medium flux test modules (creep fatigue test module, tritium release test module, liquid breeder validation module) and low flux test modules of IFMIF. In addition, the Startup Monitoring Module will be used for IFMIF commissioning. This paper is summarizing the overall current progress status of the engineering and conceptual design of the test modules in IFMIF/EVEDA. [Copyright &y& Elsevier]

Abstract: Belgium has decided to join the Broader Approach agreement. SCK•CEN has been designated by the Belgian Government to lead and coordinate the Belgian in-kind contributions in this field. Three main tasks are directly performed within SCK•CEN itself, all related to the engineering of the test cell of IFMIF: [•] Irradiation of the high flux test modules (HFTM) test rigs in the Belgian reactor BR2, for validation purposes. [•] Preliminary design of the start-up monitoring module (STUMM). [•] Conceptual design of the low flux test module (LFTM). The irradiation in the high flux BR2 reactor (Mol, Belgium) will allow validating the design of the HFTM-V (vertical lay-out) and is mostly focused on the heating system and the instrumentation performance and endurance under intense neutron flux. The STUMM is designed similar to the HFTM in order to reproduce the instantaneous irradiation conditions (flux, flux shape, temperature, etc.) of the samples. The STUMM will be loaded during the commissioning phase of the installation and will simulate the HFTM while monitoring the various parameters for characterizing the facility. Finally, the main objective of the task dedicated to the low flux test module is to pre-design the modules to be loaded in this area; but a first step is to check if the irradiation conditions fit with the ones foreseen in a DEMO-type reactor for remote components situated behind the blanket and further outwards. [Copyright &y& Elsevier]