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About 814 papers for “Loop fission”

Report on CFRMF fission product loop study

V.P. Gupta, Joy Don Baker, D. H. Meikrantz et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1985

An experimental study of tellurium plateout on stainless steel, using a fission product loop, was performed. The gamma-rays from tellurium and daughter iodine were analyzed. Analysis showed that both Te and I isotopes decayed with half-lives close to published values. The initial conclusion is that Te decay following plate-out does not provide a significant release mechanism for the respective I daughter isotopes. 11 refs., 15 figs., 4 tabs.

Cited by 0

Fission yeast Hop2-Mnd1 stimulates D-loop formation by spDmc1

Ploquin, Mickaël, Petukhova, Galina V., Morneau, Dany et al. · Figshare · 2011

<b>Copyright information:</b>Taken from "Stimulation of fission yeast and mouse Hop2-Mnd1 of the Dmc1 and Rad51 recombinases"Nucleic Acids Research 2007;35(8):2719-2733.Published online 10 Apr 2007PMCID:PMC1885673.© 2007 The Author(s) () Effect of spH2M1 in a buffer containing Mg (2.5 mM). Lane a, spDmc1 alone (4 μM); lanes b–f, effect of spH2M1 (0.25–4 μM) on spDmc1-mediated D-loop formation (4 μM); lane g, reaction with spH2M1 (4 μM) alone. () Effect of spH2M1 in a buffer containing Ca (2.5 mM). Lane a, DNA substrates (ssDNA and dsDNA) without proteins; lane b, spDmc1 alone (4 μM); lanes c–h, effect of spH2M1 (0.125–4 μM) on spDmc1-mediated D-loop formation (4 μM). () Analysis of the reversibility of the D-loop reaction by Dmc1 (4 μM) and spH2M1 (1 μM) in buffer containing Mg (2.5 mM). () Lane a, no protein (5 min reaction); lane b, no protein (60-min reaction); lanes c–i, reactions with spDmc1 and spH2M1 stopped at 1, 2.5, 5, 10, 20, 30 and 60 min, respectively; lanes j–p, spDmc1-mediated D-loop formation stopped at 1, 2.5, 5, 10, 20, 30 and 60 min, respectively. () Absence of reversibility of the D-loop reaction by spDmc1 (4 μM) and spH2M1 (1 μM) in buffer containing Ca (2.5 mM). Lane a, no protein (reaction was stopped immediately); lanes b–h, spDmc1-mediated D-loop formation stopped at 1, 2.5, 5, 10, 20, 30 and 60 min, respectively; lane i, no protein (60 min reaction); lanes j–p, reactions with spDmc1 and spH2M1 stopped at 1, 2.5, 5, 10, 20, 30 and 60 min, respectively. () Quantification of (), lanes b–g and (), lanes c–h, respectively. () Quantification of (), diamonds represent lanes c–i and squares correspond to lanes j–p. () Quantification of (), diamonds signify lanes j–p and squares correspond to lanes b–h.

Cited by 0Open access

A Novel Loop Fission Technique Inspired by Implicit Computational Complexity

Clément Aubert, Thomas Rubiano, Neea Rusch et al. · arXiv (Cornell University) · 2022

This work explores an unexpected application of Implicit Computational Complexity (ICC) to parallelize loops in imperative programs. Thanks to a lightweight dependency analysis, our algorithm allows splitting a loop into multiple loops that can be run in parallel, resulting in gains in terms of execution time similar to state-of-the-art automatic parallelization tools when both are applicable. Our graph-based algorithm is intuitive, language-agnostic, proven correct, and applicable to all types of loops, even if their loop iteration space is unknown statically or at compile time, if they are not in canonical form or if they contain loop-carried dependency. As contributions we deliver the computational technique, proof of its preservation of semantic correctness, and experimental results to quantify the expected performance gains. Our benchmarks also show that the technique could be seamlessly integrated into compiler passes or other automatic parallelization suites. We assert that this original and automatable loop transformation method was discovered thanks to the "orthogonal" approach offered by ICC.

Cited by 0Open access

Fission yeast Hop2-Mnd1 stimulates D-loop formation by spDmc1

Ploquin, Mickaël, Petukhova, Galina V., Morneau, Dany et al. · Figshare · 2011

<b>Copyright information:</b>Taken from "Stimulation of fission yeast and mouse Hop2-Mnd1 of the Dmc1 and Rad51 recombinases"Nucleic Acids Research 2007;35(8):2719-2733.Published online 10 Apr 2007PMCID:PMC1885673.© 2007 The Author(s) () Effect of spH2M1 in a buffer containing Mg (2.5 mM). Lane a, spDmc1 alone (4 μM); lanes b–f, effect of spH2M1 (0.25–4 μM) on spDmc1-mediated D-loop formation (4 μM); lane g, reaction with spH2M1 (4 μM) alone. () Effect of spH2M1 in a buffer containing Ca (2.5 mM). Lane a, DNA substrates (ssDNA and dsDNA) without proteins; lane b, spDmc1 alone (4 μM); lanes c–h, effect of spH2M1 (0.125–4 μM) on spDmc1-mediated D-loop formation (4 μM). () Analysis of the reversibility of the D-loop reaction by Dmc1 (4 μM) and spH2M1 (1 μM) in buffer containing Mg (2.5 mM). () Lane a, no protein (5 min reaction); lane b, no protein (60-min reaction); lanes c–i, reactions with spDmc1 and spH2M1 stopped at 1, 2.5, 5, 10, 20, 30 and 60 min, respectively; lanes j–p, spDmc1-mediated D-loop formation stopped at 1, 2.5, 5, 10, 20, 30 and 60 min, respectively. () Absence of reversibility of the D-loop reaction by spDmc1 (4 μM) and spH2M1 (1 μM) in buffer containing Ca (2.5 mM). Lane a, no protein (reaction was stopped immediately); lanes b–h, spDmc1-mediated D-loop formation stopped at 1, 2.5, 5, 10, 20, 30 and 60 min, respectively; lane i, no protein (60 min reaction); lanes j–p, reactions with spDmc1 and spH2M1 stopped at 1, 2.5, 5, 10, 20, 30 and 60 min, respectively. () Quantification of (), lanes b–g and (), lanes c–h, respectively. () Quantification of (), diamonds represent lanes c–i and squares correspond to lanes j–p. () Quantification of (), diamonds signify lanes j–p and squares correspond to lanes b–h.

Cited by 0Open access

Cold Trapping of Fission Products in a Stainless Steel Sodium Loop

Norimasa MITSUTSUKA, Hikaru SHIMOJIMA, Yohichi Gohshi et al. · Journal of Nuclear Science and Technology · 1977

The behavior of fission products in sodium system was studied using a cold trap installed in the Toshiba Fission Product Loop, which is a stainless steel inpile sodium loop. The fission products were generated within the liquid sodium by irradiating UO2 fuel under sodium convection. The cold trapping behavior of 95Zr, 95Nb, 132Te, 131I 137Cs and 140La (140Ba) was examined by measuring the γ-rays in the cold trap and in the sodium dump tank by means of Ge(Li) detectors. Such fission product nuclides as 131 132Te and 137Cs were found to be reversively removed by the cold trap at lower temperatures, with negligible hysteresis. The distribution coefficient K(cm) for the cold trap surface was found tobe expressible by log K=(3.08±0.17)-(0.0112±0.0006)×T(°C) for 131I, and by log K:=-(4.55±0.29) + (1830±1/140) × 1/T(K) for 137Cs. The behavior of 131I and 137Cs during cold trapping can be explained clearly by adsorption model using these K values. While 95Zr, 95Nb, 103Ru and 140La(140;Ba) also were detected in the cold trap, the efficacy of cold trapping is far lower for these nuclides than for 131I and 137Cs, and changing the cold trap temperature did not appear to have any appreciable effect on the cold trapping. Presence of 141Ce and 144Ce was not detectable in the cold trap, although small amounts of these nuclides were detected in the sodium dump tank.

Cited by 4

Cold Trapping of Fission Products in a Stainless Steel Sodium Loop

Norimasa MITSUTSUKA, Hikaru SHIMOJIMA, Yohichi Gohshi et al. · Journal of Nuclear Science and Technology · 1977

The behavior of fission products in sodium system was studied using a cold trap installed in the Toshiba Fission Product Loop, which is a stainless steel inpile sodium loop. The fission products were generated within the liquid sodium by irradiating UO2 fuel under sodium convection. The cold trapping behavior of 95Zr, 95Nb, 132Te, 131I 137Cs and 140La (140Ba) was examined by measuring the γ-rays in the cold trap and in the sodium dump tank by means of Ge(Li) detectors. Such fission product nuclides as 131 132Te and 137Cs were found to be reversively removed by the cold trap at lower temperatures, with negligible hysteresis. The distribution coefficient K(cm) for the cold trap surface was found tobe expressible by log K=(3.08±0.17)-(0.0112±0.0006)×T(°C) for 131I, and by log K:=-(4.55±0.29) + (1830±1/140) × 1/T(K) for 137Cs. The behavior of 131I and 137Cs during cold trapping can be explained clearly by adsorption model using these K values. While 95Zr, 95Nb, 103Ru and 140La(140;Ba) also were detected in the cold trap, the efficacy of cold trapping is far lower for these nuclides than for 131I and 137Cs, and changing the cold trap temperature did not appear to have any appreciable effect on the cold trapping. Presence of 141Ce and 144Ce was not detectable in the cold trap, although small amounts of these nuclides were detected in the sodium dump tank.

Cited by 6Open access

Studies of Ceramic Fuels with Use of Fission Gas Release Loop, (IV)

Muneo Handa, Shigeru Yamagishi, T. Fukuda et al. · Journal of Nuclear Science and Technology · 1974

In-pile release of fission gas from sintered UC pellets in the presence of 8–230 ppm of water vapor in the He sweep gas was measured over the temperature range of 160°–1,000°C. A very complex release behavior was observed and the mechanisms of release were deduced from the manner in which the release depended on the decay constant. It was established that the release of short-lived fission gases during irradiation was controlled mainly by pseudo-recoil, while chemical reaction between UC and water vapor, as well as knock-out, appeared to contribute much more significantly in the case of the longer-lived fission gases. The release of fission gas after reactor shutdown was shown to be governed by the UC-H2O reaction. The ratio of the release due to this reaction in reference to the total release was found to be dependent not only on the concentration of the water vapor but also on the amount present of the accumulated reaction products. Also, a discussion is given on the inordinately high release of 135mXe observed at 600°C.

Cited by 1Open access

EVALUATION OF FISSION GAS ADSORPTION TRAPS FOR ORNL-MTR-44 LOOP EXPERIMENT

R.E. Adams, W.E. Browning · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1958

A method of predicting the performance of fission gas adsorption traps containing activated charcoal is presented. This method is applied in the evaluation of the fission gas traps designed for use in the ORNL-MTR44 loop experiment. The method should also be applicable in evaluating fission gas traps contained in other reactor experiments. (auth)

Cited by 2Open access

MERARG Experimental Loop: A Forward Fitting Method for Fission Gas Release Analysis

Jimmy Losfeld, L. Desgranges, S. D. Clement et al. · IEEE Transactions on Nuclear Science · 2022

Moyens d’Etude des Rejets de Gaz de fission par Recuit (MERARG) experimental facility in LECA-STAR Laboratory at the CEA Cadarache center allows characterizing nuclear fuels with respect to the behavior of fission gases during thermal transients. In MERARG, fission gas release (F.G.R.) measurement is carried out remotely from the sample where the release occurs, in a dedicated counting chamber located outside the hot cell itself. It is therefore necessary to deconvolve the acquired experimental data in order to infer the release kinetics at the sample position. An analytical deconvolution method allows us to determine, from the experimental data, the kinetics of the F.G.R. at the sample level located in the MERARG furnace with, in some few cases, a margin of error. It is established that the F.G.R. takes the form of successive bursts depending, in part, upon temperature and characteristics of the fuel sample. For the better understanding of the mechanisms at the origin of the characteristic kinetics of F.G.R., this article aims to expose a new mathematical method for reprocessing the experimental data obtained using a forward-fitting approach, allowing us to overcome the difficulties encountered with the analytical method. This forward-fitting approach poses the question of the nature of the mechanisms underlying F.G.R. as an inverse problem. By making assumptions about these mechanisms, the forward-fitting method allows the F.G.R. interpretation by comparing them to analytically deconvoluted F.G.R. signals. This method provides a different way to analyze the annealing test data, making it possible to describe physical phenomena directly related to the gas release from the samples, such as the sudden release occurring at different temperatures.

Cited by 1

Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (I)

Seishi Yajima, Yūichirō KAMEMOTO, Muneo HAND et al. · Journal of Nuclear Science and Technology · 1967

Fission gas release from a UO2-graphite mixture was studied during irradiation with the use of the Fission Gas Release Loop in the JRR-3 reactor. The release rates of fission krypton and xenon increased proportionally with neutron flux (6×1010–6×1012 n/cm2·sec) and exponentially with temperature (400°–1,000°C). A burst of fission gas was observed when the specimen was abruptly heated to a higher temperature. These results can be explained by a mechanism whereby fission gas is trapped in defects created in graphite by fission fragments and released through annealing of the defects.

Cited by 4

Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (II)

Yūichirō KAMEMOTO, Koreyuki Shiba, Muneo Handa et al. · Journal of Nuclear Science and Technology · 1967

The γ-ray spectra of fission gases released from UO2-graphite pellets under neutron irradiation were measured. With and without separating fission gases into xenon and krypton, 25 kinds of γ-ray were observed and assigned to nine nuclides, 85mKr, 87Kr, 88Kr(88Rb), 133Xe, 135Xe, 135mXe and 138Xe (138Cs). A value of 15 min is proposed for the half-life of 138Xe, based on analysis of the decay curves. Discussion is given on problems related to determination of the release rate of each fission product through measurement of the height of each peak in the γ-ray spectrum.

Cited by 3

Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (I)

Seishi Yajima, Yūichirō KAMEMOTO, Koreyuki Shiba et al. · Journal of Nuclear Science and Technology · 1967

Fission gas release from a UO2-graphite mixture was studied during irradiation with the use of the Fission Gas Release Loop in the JRR-3 reactor. The release rates of fission krypton and xenon increased proportionally with neutron flux (6×1010–6×1012 n/cm2·sec) and exponentially with temperature (400°–1,000°C). A burst of fission gas was observed when the specimen was abruptly heated to a higher temperature. These results can be explained by a mechanism whereby fission gas is trapped in defects created in graphite by fission fragments and released through annealing of the defects.

Cited by 9Open access

Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (II)

Yūichirō KAMEMOTO, Koreyuki Shiba, Muneo Handa et al. · Journal of Nuclear Science and Technology · 1967

The ')'-ray spectra of fission gases released from U0 2 -graphite pellets under neutron irradiation were measured.With and without separating fission gases into xenon and krypton, 25 kinds of')' -ray were observed and assigned to nine nuclides, s;mKr, 87 Kr, 89 Kr ( 88 Rb), 133 Xe, 135 Xe, mmxe and 138 Xe (1 3 BCs).A value of 15 min is proposed for the half-life of 138 Xe, based on analysis of the decay curves.Discussion is given on problems related to determination of the release rate of each fission product through measurement of the height of each peak in the ')'-ray spectrum.

Cited by 4Open access

Measurement of fission product activity in the Peach Bottom Reactor primary coolant loop

Intelcom Rad Tech, San Diego, Calif. (USA) · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1976

The distribution of gamma-emitting radionuclides deposited in the primary circuit of the Peach Bottom High-Temperature Gas-Cooled Reactor (HTGR) at end-of-life has been determined by in situ gamma scanning. The work was part of the Peach Bottom End-of-Life Program and was performed by the IRT Corporation under subcontract to General Atomic Company. The measurements were made to support a design method verification exercise. The specific activity on the ducts was measured by external scans at local points with a Ge(Li) detector and by internal scans with a travelling intrinsic germanium detector (after destructive removal of trepan samples); the activity on the steam generator tube bundle was determined by traversing selected tubes with travelling CdTe detectors from the water side. Calibration measurements on mockups allowed reduction of the spectra to specific activity.

Cited by 3Open access