Design Study on Fast Reactor with Low-Enriched Uranium Modeling Fuel at Kyoto University Critical Assembly

2019 ◽  
Author(s):  
S. Jang ◽  
C. Pyeon ◽  
H. Shim ◽  
K. Song ◽  
M. Yamanaka
Keyword(s):  
Fast Reactor ◽  
Critical Assembly ◽  
Design Study ◽  
Enriched Uranium

A feasibility study on fast reactor with low-enriched uranium fuel at Kyoto University Critical Assembly

2017 ◽  
Vol 100 ◽  
pp. 60-70 ◽  
Author(s):  
Song Hyun Kim ◽  
Cheol Ho Pyeon ◽  
Akito Ohizumi ◽  
Masahiro Fukushima ◽  
Kazufumi Tsujomoto ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Fast Reactor ◽  
Critical Assembly ◽  
Uranium Fuel ◽  
Enriched Uranium

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.

Design Study on a Fast Reactor Metal Fuel Attaining Very High Burnup

2014 ◽  
Vol 187 (2) ◽  
pp. 198-207 ◽  
Author(s):  
Hirokazu Ohta ◽  
Takanari Ogata ◽  
Toru Obara
Keyword(s):  
Fast Reactor ◽  
Design Study ◽  
Metal Fuel ◽  
High Burnup ◽  
Very High

scholarly journals Neutron Generation Time in Highly-Enriched Uranium Core at Kyoto University Critical Assembly

2020 ◽  
Vol 194 (12) ◽  
pp. 1116-1127
Author(s):  
Cheol Ho Pyeon ◽  
Masao Yamanaka ◽  
Tomohiro Endo ◽  
Go Chiba ◽  
Willem F. G Van Rooijen ◽  
...  
Keyword(s):  
Generation Time ◽  
Critical Assembly ◽  
Neutron Generation ◽  
Enriched Uranium

Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor

2011 ◽  
Vol 48 (4) ◽  
pp. 463-471 ◽  
Author(s):  
Kazumi AOTO ◽  
Nariaki UTO ◽  
Yoshihiko SAKAMOTO ◽  
Takaya ITO ◽  
Mikio TODA ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Design Study

A CONCEPTUAL DESIGN STUDY OF POOL-TYPE SODIUM-COOLED FAST REACTOR WITH ENHANCED ANTI-SEISMIC CAPABILITY

2019 ◽  
Vol 2019.27 (0) ◽  
pp. 1651
Author(s):  
Shigenobu Kubo ◽  
Yoshitaka Chikazawa ◽  
Hiroyuki Ohshima ◽  
Masato Uchita ◽  
Takayuki Miyagawa ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Design Study ◽  
Pool Type

Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle

2004 ◽  
Vol 41 (3) ◽  
pp. 307-314 ◽  
Author(s):  
Takeshi TAKATA ◽  
Yoshikazu KOMA ◽  
Koji SATO ◽  
Masayoshi KAMIYA ◽  
Atsuhiro SHIBATA ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Design Study ◽  
Fast Reactor Fuel
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