scholarly journals Measurement of highly enriched uranium metal buttons with the high-level neutron coincidence counter operating in the active mode

1980 ◽  
Author(s):  
J.E. Foley
Keyword(s):  
Uranium Metal ◽  
Active Mode ◽  
Coincidence Counter ◽  
Enriched Uranium ◽  
High Level

scholarly journals High-level neutron coincidence counter (HLNCC): users' manual

1979 ◽  
Author(s):  
M.S. Krick ◽  
H.O. Menlove
Keyword(s):  
Coincidence Counter ◽  
High Level

CAREM X INPRO Case Study

2004 ◽  
Author(s):  
Pablo C. Florido ◽  
Dari´o Delmastro ◽  
Daniel Brasnarof ◽  
Osvaldo E. Azpitarte
Keyword(s):  
Nuclear Reactor ◽  
Fuel Cycle ◽  
High Level Waste ◽  
Fuel Cycles ◽  
Surface Intermediate ◽  
Geological Repository ◽  
Enriched Uranium ◽  
Intermediate Storage ◽  
High Level

Argentina is performing CAREM X Nuclear System Case Study based on CAREM nuclear reactor and Once Through Fuel Cycle, using SIGMA for enriched uranium production, and a deep geological repository for final disposal of high level waste after surface intermediate storage in horizontal natural convection silos, to verify INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles) methodology. Projections show that developing countries could play a crucial role in the deployment of nuclear energy, in the next fifty years. This case study will be highly useful for checking INPRO methodology for this scenario. In this contribution to ICONE 12, the preliminary findings of the Case Study are presented, including proposals to improve the INPRO methodology.

Prompt-Neutron Lifetime in Critical Enriched-Uranium Metal Cylinders and Annuli

1964 ◽  
Vol 20 (1) ◽  
pp. 60-65 ◽  
Author(s):  
John T. Mihalczo
Keyword(s):  
Prompt Neutron ◽  
Neutron Lifetime ◽  
Uranium Metal ◽  
Enriched Uranium

scholarly journals ENRICHED URANIUM-METAL MEASUREMENTS, NO. 1.

1967 ◽  
Author(s):  
G. Tuck
Keyword(s):  
Uranium Metal ◽  
Enriched Uranium

Critical Mass Irregularity of Steel-Moderated Enriched Uranium Metal Assemblies with Composite Steel-Oil Reflectors

1970 ◽  
Vol 39 (3) ◽  
pp. 320-328 ◽  
Author(s):  
Donald C. Coonfield ◽  
Grover Tuck ◽  
Harold E. Clark ◽  
Bruce B. Ernst
Keyword(s):  
Critical Mass ◽  
Uranium Metal ◽  
Enriched Uranium ◽  
Composite Steel

Reactor Physics Parameters of 1.03% Enriched Uranium Metal, D2O Moderated Lattices

1968 ◽  
Vol 32 (3) ◽  
pp. 283-291 ◽  
Author(s):  
Walter H. D’Ardenne ◽  
Henry E. Bliss ◽  
David D. Lanning ◽  
Irving Kaplan ◽  
Theos J. Thompson
Keyword(s):  
Reactor Physics ◽  
Uranium Metal ◽  
Enriched Uranium

Manufacturing low enriched uranium metal by magnesiothermic reduction of UF4

2017 ◽  
Vol 110 ◽  
pp. 874-885 ◽  
Author(s):  
M. Durazzo ◽  
A.M. Saliba-Silva ◽  
I.C. Martins ◽  
E.F. Urano de Carvalho ◽  
H.G. Riella
Keyword(s):  
Magnesiothermic Reduction ◽  
Uranium Metal ◽  
Enriched Uranium

ACR-1000™ Level 1 PSA Summary

2009 ◽  
Author(s):  
U. Menon ◽  
S. Aprodu ◽  
R. Bettig ◽  
R. Henderson ◽  
T. Ha ◽  
...  
Keyword(s):  
Cooling System ◽  
Safety Margin ◽  
Water System ◽  
Operation Performance ◽  
Light Water ◽  
Level 1 ◽  
Enriched Uranium ◽  
Core Cooling ◽  
Four Quadrant ◽  
High Level

The ACR-1000™ developed by Atomic Energy of Canada Limited (AECL) is a 1200 MWe - pressure tube type, light-water-cooled and heavy-water-moderated reactor, which has evolved from the well-established CANDU™ line of reactors. It retains the basic proven CANDU design features while incorporating innovations and state-of-the-art technologies to ensure fully competitive safety, operation, performance and economics. The major innovation in the ACR-1000 is the use of slightly enriched uranium fuel and light water coolant. ACR-1000 is a four-quadrant design (for easier maintenance and improved reliability). There are five safety systems in the ACR-1000; (i) two independent, diverse and fast acting shutdown systems (SDS1 and SDS2), which are physically and functionally independent from each other and from the reactor regulating system; (ii) Emergency core cooling system; (iii) Emergency Feedwater system; and (iv) Containment system, which includes a strong steel-lined containment structure. In addition the Reserve water system provides feedwater to the heat transport system, steam generators, moderator and shield cooling system for beyond design basis accidents. The Level 1 Probabilistic Safety Assessment (PSA) is conducted in support of the design phase of the ACR-1000. The purpose of Level 1 PSA is to identify whether the ACR-1000 design targets and the regulatory safety goal for severe core damage frequency (SCDF) are met with adequate margin and provide design feedback. An interim Level 1 PSA was conducted for internal at-power events. Interim assessments were conducted for shutdown state, internal fire and flood at-power events. An interim seismic margin assessment was conducted for the seismic events. The Level 1 PSA results show that the ACR™ design targets and safety goal for SCDF are met with significant safety margin. Based on the ACR-1000 Level 1 PSA, the accident behaviours of the ACR-1000 are well understood and their consequences can be predicted with a high-level of confidence. It also provides sufficient assurance that the release based regulatory safety goals are achievable for ACR-1000. The Level 1 PSA results also signify a robust design that provides a strong foundation for the ACR-1000 design. The paper summarizes the Level 1 PSA program, methodology followed, the results obtained, and insights gained during the development of the ACR-1000 Level 1 PSA.

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