Measurement of the delayed-neutron yields in the fission of233U,236U,237Np,240Pu, and241Pu by neutrons from the spectrum of a fast reactor

1989 ◽  
Vol 66 (2) ◽  
pp. 115-118 ◽  
Author(s):  
A. N. Gudkov ◽  
V. M. Zhivun ◽  
A. V. Zvonarev ◽  
V. V. Kovalenko ◽  
A. B. Koldobskii ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Delayed Neutron ◽  
Fission Of233u

Delayed Neutron Data for Fast Reactor Analysis

1973 ◽  
Vol 50 (3) ◽  
pp. 208-215 ◽  
Author(s):  
J. E. Cahalan ◽  
K. O. Ott
Keyword(s):  
Fast Reactor ◽  
Delayed Neutron ◽  
Neutron Data

scholarly journals Neutronic Analysis of LEU-started Molten Chloride Fast Reactor without Fuel Reprocessing

2021 ◽  
Vol 4 (1) ◽  
pp. 8
Author(s):  
R. Andika Putra Dwijayanto ◽  
Andang Widi Harto
Keyword(s):  
Fast Reactor ◽  
Molar Fraction ◽  
Chloride Salt ◽  
Inherent Safety ◽  
Delayed Neutron ◽  
Core Zone ◽  
Molten Chloride ◽  
Enriched Uranium ◽  
Fuel Reprocessing ◽  
Coefficient Of Reactivity

One of the rarely explored molten salt reactor (MSR) designs is the molten chloride fast reactor (MCFR). This MSR design employs chloride salt instead of fluoride and operated in a fast spectrum. MCFR brings all the advantages of an MSR including breeding whilst being able to burn plutonium and minor actinides efficiently. Since not many countries have access to civilian plutonium, MCFR can also be started using low-enriched uranium (LEU). This study is an initial neutronic analysis of an MCFR using LEU as its startup fuel. Parameters analyzed are conversion ratio (CR) and its neutronic safety, namely effective delayed neutron fraction (βeff), temperature coefficient of reactivity (TCR), and void coefficient of reactivity (VCR). The core is divided into Core Zone and Blanket Zone. The fuel composition of NaCl-UCl3 with a molar fraction ratio of 60:40 and 50:50 is used in Core Zone and Blanket Zone, respectively. The neutronic calculation is performed using MCNP6 code with ENDF/B-VII library. For reference geometry, CR is valued at 0.9298, βeff at 0.00731, TCR at -19.8 pcm/°C, and average VCR at -154.31 pcm/void%. Thereby, the MCFR fulfills inherent safety criteria. Although its value is remarkably high, CR can be further optimized by modifying the separator and reflector material.

scholarly journals Uncertainty Evaluation of Effective Delayed Neutron Fraction βeffof Typical Proto-type Fast Reactor

1999 ◽  
Vol 36 (1) ◽  
pp. 61-80 ◽  
Author(s):  
Atsushi ZUKERAN ◽  
Hiroshi HANAKI ◽  
Shusaku SAWADA ◽  
Takayuki SUZUKI
Keyword(s):  
Fast Reactor ◽  
Uncertainty Evaluation ◽  
Delayed Neutron

Ex-Vessel Delayed Neutron Detection Systems for the ASTRID Sodium-Cooled Fast Reactor

2018 ◽  
Vol 65 (9) ◽  
pp. 2502-2509 ◽  
Author(s):  
Romain Coulon ◽  
Emmanuel Rohee ◽  
Jonathan Dumazert ◽  
Sara Garti ◽  
Philippe Filliatre ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Neutron Detection ◽  
Delayed Neutron ◽  
Detection Systems

scholarly journals Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor

2018 ◽  
Vol 170 ◽  
pp. 04006
Author(s):  
Romain Coulon ◽  
Emmanuel Rohée ◽  
Jonathan Dumazert ◽  
Sara Garti ◽  
Philippe Filliatre ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Fast Reactor ◽  
Simulation Study ◽  
Detection System ◽  
Neutron Detection ◽  
Delayed Neutron ◽  
Fast Reactors ◽  
Detection Systems ◽  
Transport Code

Delayed neutron detection systems are key apparati in Sodium cooled Fast Reactors to prevent safety accidents. Based on the feedbacks from Phenix and Superphenix, DND systems are studied by means of the Monte-Carlo particles transport code MCNP6. Promising designs are proposed and investigated as a result of the simulation study.

Conception of delayed neutron detector blocks in a sodium cooled fast reactor

2021 ◽  
Vol 371 ◽  
pp. 110933
Author(s):  
P. Filliatre ◽  
C. Jammes ◽  
C. Ding ◽  
L. Desgranges ◽  
R. Coulon
Keyword(s):  
Fast Reactor ◽  
Neutron Detector ◽  
Delayed Neutron
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