In-pile loop irradiation studies of organic coolant materials : progress report, October 1, 1965 - December 31, 1965

"Issued: April 1, 1966.""AEC Research and Development Report"--Cover"MIT-334-48 ,Reactor Technology, Standard TID 4500."Includes bibliographical references (leaf 28)Progress report; October 1, 1965 - December 31, 1965M.I.T. project no. DSR 9819U.S. Atomic Energy Commission, Savannah River Operations Office contract no. AT(38-1)-33

Radiopyrolysis

Statement of responsibility on title-page reads: E.A. Mason, T.H. Timmins, D.T. Morgan, and W.N. Bley"Issued: October 1966.""MIT-334-70 Reactor Technology."Also issued by T.H. Timmins and supervised by E.A. Mason as an Sc. D. thesis , Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1967Includes bibliographical references (pages A6.1-A6.7)MIT DSR Project no. 79819Work performed for the Savannah River Operations Office, U.S. Atomic Energy Commission under Contract no. AT(38-1)-33

Friction factor and heat transfer correlation for irradiated organic coolants

"September 1965."Series statement handwritten on cover"MIT-334-23 Chemistry."Also written as an M.S. theses written by the first author and advised by the second author, Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1966Includes bibliographical references (pages 163-165)M.I.T. DSR Project no. 9819Work performed for the Savannah River Operations Office, U.S. Atomic Energy Commission under contract no. AT(38-1)-33

Organic moderator-coolant in-pile irradiation loop for the MIT nuclear reactor

Includes bibliographical references (leaf 34)Progress report; to July 1, 1961Work performed under contract with Atomics International to November, 1960, and under contract with the Atomic Energy Commission, Idaho Operations Office, after November, 1960Division of Sponsored Research Project no. 8710Atomics International contract no. N9-S-514Atomic Energy Commission contract no. AT(10-1)-106

Implications of an HRA framework for quantifying human acts of commission and dependency: Development of a methodology for conducting an integrated HRA/PRA

To support the development of a refined human reliability analysis (HRA) framework, to address identified HRA user needs and improve HRA modeling, unique aspects of human performance have been identified from an analysis of actual plant-specific events. Through the use of the refined framework, relationships between the following HRA, human factors and probabilistic risk assessment (PRA) elements were described: the PRA model, plant states, plant conditions, PRA basic events, unsafe human actions, error mechanisms, and performance shaping factors (PSFs). The event analyses performed in the context of the refined HRA framework, identified the need for new HRA methods that are capable of: evaluating a range of different error mechanisms (e.g., slips as well as mistakes); addressing errors of commission (EOCs) and dependencies between human actions; and incorporating the influence of plant conditions and multiple PSFs on human actions. This report discusses the results of the assessment of user needs, the refinement of the existing HRA framework, as well as, the current status on EOCs, and human dependencies

NRC support for the Kalinin (VVER) probabilistic risk assessment

The US Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation have been working together since 1994 to carry out a probabilistic risk assessment (PRA) of a VVER-1000 in the Russian Federation. This was a recognition by both parties that this technology has had a profound effect on the discipline of nuclear reactor safety in the West and that the technology should be transferred to others so that it can be applied to Soviet-designed plants. The NRC provided funds from the Agency for International Development and technical support primarily through Brookhaven National Laboratory and its subcontractors. The latter support was carried out through workshops, by documenting the methodology to be used in a set of guides, and through periodic review of the technical activity. The result of this effort to date includes a set of procedure guides, a draft final report on the Level 1 PRA for internal events (excluding internal fires and floods), and progress reports on the fire, flood, and seismic analysis. It is the authors belief that the type of assistance provided by the NRC has been instrumental in assuring a quality product and transferring important technology for use by regulators and operators of Soviet-designed reactors. After a thorough review, the report will be finalized, lessons learned will be applied in the regulatory and operational regimes in the Russian Federation, and consideration will be given to supporting a containment analysis in order to complete a simplified Level 2 PRA

Selective Uncoupling of Individual Mitochondria within a Cell Using a Mitochondria-Targeted Photoactivated Protonophore

Depolarization of an individual mitochondrion or small clusters of mitochondria within cells has been achieved using a photoactivatable probe. The probe is targeted to the matrix of the mitochondrion by an alkyltriphenylphosphonium lipophilic cation and releases the protonophore 2,4-dinitrophenol locally in predetermined regions in response to directed irradiation with UV light via a local photolysis system. This also provides a proof of principle for the general temporally and spatially controlled release of bioactive molecules, pharmacophores, or toxins to mitochondria with tissue, cell, or mitochondrion specificity