Submarine record of volcanic island construction and collapse in the Lesser Antilles arc: First scientific drilling of submarine volcanic island landslides by IODP Expedition 340

IODP Expedition 340 successfully drilled a series of sites offshore Montserrat, Martinique and Dominica in the Lesser Antilles from March to April 2012. These are among the few drill sites gathered around volcanic islands, and the first scientific drilling of large and likely tsunamigenic volcanic island-arc landslide deposits. These cores provide evidence and tests of previous hypotheses for the composition and origin of those deposits. Sites U1394, U1399, and U1400 that penetrated landslide deposits recovered exclusively seafloor-sediment, comprising mainly turbidites and hemipelagic deposits, and lacked debris avalanche deposits. This supports the concepts that i/ volcanic debris avalanches tend to stop at the slope break, and ii/ widespread and voluminous failures of pre-existing low-gradient seafloor sediment can be triggered by initial emplacement of material from the volcano. Offshore Martinique (U1399 and 1400), the landslide deposits comprised blocks of parallel strata that were tilted or micro-faulted, sometimes separated by intervals of homogenized sediment (intense shearing), while Site U1394 offshore Montserrat penetrated a flat-lying block of intact strata. The most likely mechanism for generating these large-scale seafloor-sediment failures appears to be propagation of a decollement from proximal areas loaded and incised by a volcanic debris avalanche. These results have implications for the magnitude of tsunami generation. Under some conditions, volcanic island landslide deposits comprised of mainly seafloor sediment will tend to form smaller magnitude tsunamis than equivalent volumes of subaerial block-rich mass flows rapidly entering water. Expedition 340 also successfully drilled sites to access the undisturbed record of eruption fallout layers intercalated with marine sediment which provide an outstanding high-resolution dataset to analyze eruption and landslides cycles, improve understanding of magmatic evolution as well as offshore sedimentation processes. This article is protected by copyright. All rights reserved

The ATLAS Trigger/DAQ Authorlist, version 3.0

This is the ATLAS Trigger/DAQ Authorlist, version 3.0, 11 September 200

The ATLAS Trigger/DAQ Authorlist, version 2.0

This is the ATLAS Trigger/DAQ Authorlist, version 2.0, 31 July 200

The ATLAS Trigger/DAQ Authorlist, version 3.1

This is the ATLAS Trigger/DAQ Authorlist, version 3.1, 17 September 200

Primary creep of UO/sub 2/ above 2000/sup 0/C

A technique for measuring primary creep was developed which facilitates rapid load application to high temperature creep samples. Creep strain measurements for times as short as one second can be made. The strain as a function of time has a logarithmic relationship with a time exponent of 0.7 +- 0.1. Although the resulting expression is in conflict with the normal way of describing the high temperature deformation of fuel under stress, it is possible to incorporate so-called steady state creep into the proposed primary creep relationship. (FS

In situ tritium recovery from Li{sub 2}O irradiated in fast neutron flux: BEATRIX-II effect of gas composition

The BEATRIX-II irradiation experiment is an in-situ tritium recovery experiment to evaluate the tritium release characteristics of Li{sub 2}O and to characterize its stability under fast neutron irradiation to extended burnups. This is an IEA sponsored experiment which is being carried out in the Materials Open Test Assembly of FFTF. The participants are Japan, Canada and the US. The in-situ tritium recovery experiment includes two specimens: a thin annular specimen capable of temperature changes and a larger temperature-gradient specimen. Two other papers have been presented this week at ICFRM-5 which dealt with the results to date. At this workshop I will discuss the effects of gas composition changes that have been observed in BEATRIX-II, Phase 1 and the implications that these observations have on the operation of ion chambers

BEATRIX-II, phase II: Data summary report

The BEATRIX-II experimental program was an International Energy Agency sponsored collaborative effort between Japan, Canada, and the United States to evaluate the performance of ceramic solid breeder materials in a fast-neutron environment at high burnup levels. This report addresses the Phase II activities, which included two in situ tritium-recovery canisters: temperature-change and temperature-gradient. The temperature-change canister contained a Li{sub 2}O ring specimen that had a nearly uniform temperature profile and was capable of temperature changes between 530 and 640{degrees}C. The temperature-gradient canister contained a Li{sub 2}ZrO{sub 3} pebble bed operating under a thermal gradient of 440 to 1100{degrees}C. Postirradiation examination was carried out to characterize the Phase II in situ specimens and a series of nonvented capsules designed to address the compatibility of beryllium with lithium-ceramic solid-breeder materials. The results of the BEATRIX-II, Phase II, irradiation experiment provided an extensive data base on the in situ tritium-release characteristics of Li{sub 2}O and Li{sub 2}ZrO{sub 3} for lithium burnups near 5%. The composition of the sweep gas was found to be a critical parameter in the recovery of tritium from both Li{sub 2}O and Li{sub 2}ZrO{sub 3}. Tritium inventories measured confirmed that Li{sub 2}O and Li{sub 2}ZrO{sub 3} exhibited very low tritium retention during the Phase II irradiation. Tritium inventories in Li{sub 2}ZrO{sub 3} after Phase II tended to be larger than those found for Li{sub 2}ZrO{sub 3} in other in situ experiments, but the larger values may reflect the larger generation rates in BEATRIX-II. A series of 20 capsules was irradiated to determine the compatibility of lithium ceramics and beryllium under conditions similar to a fusion blanket. It is concluded that Li{sub 2}O and Li{sub 2}ZrO{sub 3} should remain leading candidates for use in a solid-breeder fusion-blanket application

BEATRIX-II Program: ANNEX-III to IEA implementing agreement for a programme of research and development on radiation damage in fusion materials. Fourth annual report, January 1991--December 1991

The BEATRIX-II experiment is an International Energy Agency (IEA) sponsored collaborative experiment between Japan, Canada, and the United States. This is an in situ tritium recovery experiment conducted to evaluate the performance of ceramic solid breeder materials in a fast neutron environment to high burnup levels. The experiment was carried out in the Fast Flux Test Facility (FFTF), located on the Hanford site near Richland, Washington, and was operated by Westinghouse Hanford Company (WHC). Pacific Northwest Laboratory, Richland (PNL), Richland, Washington, together with the Japan Atomic Energy Research Institute (JAERI) and Atomic Energy of Canada Limited (AECL) Research are conducting the experiment. The objective of the BEATRIX-II experiment is to design, conduct, and evaluate the in situ recovery of tritium from solid breeder materials during neutron irradiation in the FFTF. During the experiment, the performance of candidate solid breeder materials is continuously monitored with respect to temperature stability and tritium release. The phase I experiment was irradiated to lithium burnups of 5% while the goal for Phase II was to irradiate to burnups as high as 8%

BEATRIX-2 Program third annual report, January 1990--December 1990. ANNEX-3 to IEA implementing agreement for a programme of research and development on radiation damage in fusion materials

The BEATRIX-2 experiment is an International Energy Agency (IEA) sponsored collaborative experiment between Japan, Canada, and the United States. The purpose of the experiment is to evaluate the performance of ceramic solid breeder materials in a fast neutron environment. To do this, an in-situ tritium recovery experiment is being conducted in the Fast Flux Test Facility (FFTF), located on the Hanford site near Richland, Washington, and operated by Westinghouse Hanford Company (WHC). The Pacific Northwest Laboratory (PNL), Richland, Washington, together with the Japan Atomic Energy Research Institute (JAERI) and Atomic Energy of Canada Limited (AECL) are responsible for conducting the experiment. This work is divided into two phases: Phase 1 was irradiated from January 1990 until March 1991 in Cycle 11 of FFTF, while Phase 2 will be irradiated in Cycle 12, which began in June 1991 and is scheduled to continue until approximately October of 1991 for 300 effective full power days (EFPD)