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[en] This section treats of the following legal text: Sixteenth Amendment to the Atomic Energy Act (16. Amendment) of 10 July 2018. The German Bundestag has adopted the following Act: Article 1. Amendment to the Atomic Energy Act: The following Sections 7e to 7g shall be inserted after Section 7d Atomic Energy Act in the version promulgated on 15 July 1985 (Federal Law Gazette I p. 1565), as most recently amended by Article 2(2) of the Act of 20 July 2017 (Federal Law Gazette I p. 2808): Section 7e - Financial settlement for investments made; Section 7f - Financial settlement for electricity volumes; Section 7g - Administrative procedure; Article 2. Amendment of the Code of Administrative Court Procedure: Section 48(1) Sentence 1 Code of Administrative Court Procedure in the version promulgated on 19 March 1991 (Federal Law Gazette I p. 686), as most recently amended by Article 5(2) of the Act of 8 October 2017 (Federal Law Gazette I p. 3536), shall be amended by insertion of the following Number 1a after Number 1: 1a. the merits and amount of financial settlement claims pursuant to Section 7e and Section 7f of the Atomic Energy Act; Article 3. Entry into force: This Act shall enter into force on the day when the European Commission gives its approval under State-aid law or makes a binding declaration to the effect that no such approval shall be required; the Federal Ministry in charge of nuclear safety and radiation protection shall announce the date of the entry into force and do this by means of the Federal Law Gazette.
[en] This report published by the Swiss Nuclear Safety Inspectorate ENSI presents an assessment report concerning the decommissioning of the AGN-211-P research reactor at the University of Basel. The legal requirements placed on the project are reviewed, as are its aims. The functions and history of the installation are reviewed. The project concept, its various phases and the time plan for its implementation are looked at. The main aspects of the decommissioning project are examined including nuclear safety and radiation protection. Organisational aspects are examined and proposals for the disposal of radioactive wastes and materials is discussed.
[en] The work presented in this paper discusses issues related to post Fukushima requirements and investigates the performance of some severe accident safety features for AES-92 design to cope with Fukushima accident and post Fukushima requirements. The paper investigates the Passive Residual Heat Removal System (PRHRS) capability for removing all the core decay heat without any AC power source or even any operator intervention to provide a significant grace time, during which essentially passive natural processes can provide adequate cooling, before any operator action is needed. It also investigates the compliance of the design of severe accidents safety features of AES-92 model, which is the proposed design to be constructed in Jordan, with IAEA post Fukushima safety requirements (SSR-2/1). A deterministic safety code will be used to model the essential components of the primary, secondary loop and passive safety systems with corresponding control systems for AES-92 model to analytically address the performance of the PRHRS taking into the severe environmental conditions of the NPP site in Jordan. (author)