1,015 research outputs found
Acroneuria frisoni Stark & Brown
No full textAcroneuria frisoni Stark & Brown. This is the most frequently collected Acroneuria in the southern Midwest. It is known from the western Ozark Mountains through Maryland, north to Ontario and south to North Carolina (Chabot 2010). Although this species once inhabited streams in the till plain of north central Indiana and Illinois (Grubbs 2004, DeWalt et al. 2005), there are no recent records from this region. We have since located one population in northeastern Indiana at the till plain/drift plain boundary. IN, Steuben Co., Fish Creek, 3.7 km E Hamilton along CR 775S, Douglas Woods Nature Preserve, 41.5327, -84.8688, 6/23/2006, R.E. DeWalt, 3♂, ♀ (INHS).Published as part of DeWalt, R. Edward & Grubbs, Scott A., 2011, Updates To The Stonefly Fauna Of Illinois And Indiana, pp. 31-50 in Illiesia 7 (3) on page 39, DOI: 10.5281/zenodo.476039
Isoperla frisoni Illies
No full textIsoperla frisoni Illies. This species is known from Indiana north through the upper Great Lakes region and from North Carolina north through eastern Canada (DeWalt et al. 2010). Frison (1937) originally described it as Isoperla truncata (a homonym) with a paratype from the Yellow River, a sand-bottomed stream in northern Indiana. This species has never been collected from Illinois, but could be present in the Kankakee and Rock River drainages. We present a few new locations in Indiana, including one recent record. IN, LaGrange Co., Pigeon Creek at [CR] 1100 E, E Pigeon River Fish-Game Area, 41.6728, - 85.21492, 5/20/1972, ♀ (PERC); LaPorte Co., Trail Creek, Michigan City, [41.7237, -86.8719], 6/21/1957, J. Lowe, 3♂ (CNC); same location, 4/22/2007, R.E. DeWalt, 6N (INHS).Published as part of DeWalt, R. Edward & Grubbs, Scott A., 2011, Updates To The Stonefly Fauna Of Illinois And Indiana, pp. 31-50 in Illiesia 7 (3) on page 45, DOI: 10.5281/zenodo.476039
BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) - Generation Methodology and Preliminary Testing of two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry
No full textTwo broad-group coupled neutron/photon working cross section libraries in FIDO-ANISN format, dedicated to LWR shielding and pressure vessel dosimetry applications, were generated following the methodology recommended by the US ANSI/ANS-6.1.2-1999 (R2009) standard. These libraries, named BUGJEFF311.BOLIB and BUGENDF70.BOLIB, are respectively based on JEFF-3.1.1 and ENDF/B-VII.0 nuclear data and adopt the same broad-group energy structure (47 n + 20 γ) of the ORNL BUGLE-96 similar library. They were respectively obtained from the ENEA-Bologna VITJEFF311.BOLIB and VITENDF70.BOLIB libraries in AMPX format for nuclear fission applications through problem-dependent cross section collapsing with the ENEA-Bologna 2007 revision of the ORNL SCAMPI nuclear data processing system. Both previous libraries are based on the Bondarenko self-shielding factor method and have the same AMPX format and fine-group energy structure (199 n + 42 γ) as the ORNL VITAMIN-B6 similar library from which BUGLE-96 was obtained at ORNL. A synthesis of a preliminary validation of the cited BUGLE-type libraries, performed through 3D fixed source transport calculations with the ORNL TORT-3.2 SN code, is included. The calculations were dedicated to the PCA-Replica 12/13 and VENUS-3 engineering neutron shielding benchmark experiments, specifically conceived to test the accuracy of nuclear data and transport codes in LWR shielding and radiation damage analyses. © 2016 Owned by the authors, published by EDP Sciences
Summary results of 2005 activation calculation in support of ITER. EFDA Task No. TW5-TSS-SEA4.1/D3, Final Report, ENEA FUS-TN-SA-SE-R-135
No full textDuring 2005 various analyses have been performed by ENEA in the frame of the EFDA task TW5-TSS-SEA4.1 in support of ITER licensing. Two aspects have been assessed (milestones M1 and M2, respectively):
M1: the first one is related to the impact of the cobalt content into the materials of the Vacuum Vessel, with respect to their clearance possibility and,
M2: the second one is related to the calculation of the activation of ITER coolant pipes that have been irradiated in OSIRIS fission reactor and then inserted into the CORELE-2 loop (in CEA centre of Cadarache) for material release rate tests and PACTITER code validation.
The results related to M1 and M2 were presented in details and discussed respectively in two ENEA reports (deliverables D1 and D2, respectively):
D1: ENEA FUS-TN-SA-SE-R-131, July 2005, plus Addendum (September 2005).
D2: ENEA FUS-TN-SA-SE-R-133, October 2005.
The relevant results obtained are summarised into this final report (Deliverable D3), together with updated analyses of the clearance possibility of ITER Vacuum Vessel materials when the new (August 2004) unconditional clearance levels given in IAEA Safety Guide RS-G-1.7 are used instead of those given in the older (January 1996) IAEA TECDOC-855. The relevant outcomes from that updated analysis are:
• the 430 ferritic steel and the SS 304B4 steel of the Outboard VV zone VVSHDO(2) result to be clearable after a longer time if compared with the previous analysis results when TECDOC-855 clearance level data were employed. This is particularly significant for the SS 304B4 steel that becomes clearable only after about 6000 years (with respect to the 90 years of the previous analysis).
• the remarkable change for the VVSHDO(2) – SS 304B4 steel is due to the highest contribute (at 100 years cooling time) from the Ni-63, which is now (i.e. with the RS-G-1.7) of about 40% with respect to the older (i.e. with the TECDOC-855) value of about 10%.
Detailed results of the new activation calculation are given in the appendix
Three-Dimensional (X,Y,Z) Deterministic Analysis of the PCA-Replica Neutron Shielding Benchmark Experiment using the TORT-3.2 Code and Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry
No full textThe PCA-Replica 12/13 (H2O/Fe) neutron shielding benchmark experiment was analysed using the ORNL TORT-3.2 3D SN code. PCA-Replica, specifically conceived to test the accuracy of nuclear data and transport codes employed in LWR shielding and radiation damage calculations, reproduces a PWR ex-core radial geometry with alternate layers of water and steel including a PWR pressure vessel simulator. Three broad-group coupled neutron/photon working cross section libraries in FIDO-ANISN format with the same energy group structure (47 n + 20 γ) and based on different nuclear data were alternatively used: the ENEA BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) libraries and the ORNL BUGLE-96 (ENDF/B-VI.3) library. Dosimeter cross sections derived from the IAEA IRDF-2002 dosimetry file were employed. The calculated reaction rates for the Rh-103(n,n′)Rh-103 m, In-115(n,n′)In-115m and S-32(n,p)P-32 threshold activation dosimeters and the calculated neutron spectra are compared with the corresponding experimental results
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