Conceptual Design study of Small Long-life Gas Cooled Fast Reactor With Modified CANDLE Burn-up Scheme

2010 ◽  
Author(s):  
A. Nur Asiah ◽  
Zaki Su’ud ◽  
A. Ferhat ◽  
H. Sekimoto ◽  
Zaki Su’ud ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Design Study ◽  
Long Life

scholarly journals Conceptual design study on very small long-life gas cooled fast reactor using metallic natural Uranium-Zr as fuel cycle input

2014 ◽  
Author(s):  
Fiber Monado ◽  
Menik Ariani ◽  
Zaki Su'ud ◽  
Abdul Waris ◽  
Khairul Basar ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Design Study ◽  
Long Life

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

scholarly journals A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

2020 ◽  
Vol 7 (3) ◽  
pp. 19-00489-19-00489
Author(s):  
Shigenobu KUBO ◽  
Yoshitaka CHIKAZAWA ◽  
Hiroyuki OHSHIMA ◽  
Masato UCHITA ◽  
Takayuki MIYAGAWA ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Design Study ◽  
Pool Type

ICONE11-36431 Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle

2003 ◽  
Vol 2003 (0) ◽  
pp. 380
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

Preliminary design study of the ultra long life fast reactor

1993 ◽  
Vol 140 (2) ◽  
pp. 251-260 ◽  
Author(s):  
Zaki Su'ud ◽  
Hiroshi Sekimoto
Keyword(s):  
Fast Reactor ◽  
Preliminary Design ◽  
Design Study ◽  
Long Life

Conceptual Design Study of Small 400 MWt Pb-Bi Cooled Modified Candle Burn-Up Based Long Life Fast Reactors

2014 ◽  
Vol 983 ◽  
pp. 353-356 ◽  
Author(s):  
Zaki Suud ◽  
H. Sekimoto
Keyword(s):  
Conceptual Design ◽  
Fuel Cycle ◽  
Volume Fraction ◽  
Natural Uranium ◽  
Multiplication Factor ◽  
Fast Reactors ◽  
Design Study ◽  
Accumulation Pattern ◽  
Pattern Change ◽  
Long Life

In this paper conceptual design study of modified CANDLE burn-up scheme based 400 MWt small long life Pb-Bi Cooled Fast Reactors with natural Uranium as Fuel Cycle Input has been performed. In this study the reactor cores are subdivided into 10 parts with equal volume in the axial directions. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of I’th region into I+1 region after the end of 10 years burn-up cycle. For small reactor core, it is important to apply high breeding material, so that high volume fraction of 60% fuel volume fraction nitride fuel is applied. The effective multiplication factor initially at 1.005 but then continuously increases during 10 years of burn-up. The peak power density initially about 307 W/cc but then continuously decreases to 268 at the end of 10 years burn-up cycle. Infinite multiplication factor pattern change, conversion ratio pattern change, and Pu-239 accumulation pattern change shows strong acceleration of plutonium production in the first region which is located near the 10th region. Maximum discharged burn-up is 31.2% HM.

scholarly journals Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling

2016 ◽  
Vol 82 ◽  
pp. 03008 ◽  
Author(s):  
Ratna Dewi Syarifah ◽  
Yacobus Yulianto ◽  
Zaki Su’ud ◽  
Khairul Basar ◽  
Dwi Irwanto
Keyword(s):  
Fast Reactor ◽  
Design Study ◽  
Long Life

Study on Ultra-Long Life, Small U-ZR Metallic Fuelled Core With Burnable Poison

2002 ◽  
Author(s):  
Kenji Tsuji ◽  
Hiromitsu Inagaki ◽  
Akira Nishikawa ◽  
Hisato Matsumiya ◽  
Yoshiaki Sakashita ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Major Part ◽  
Reactor Core ◽  
Core Concept ◽  
Safety Requirements ◽  
Burnable Poison ◽  
The Core ◽  
Long Lifetime ◽  
Long Life

A conceptual design for a 50MWe sodium cooled, U-Pu-Zr metallic fuelled, fast reactor core, which aims at a core lifetime of 30 years, has been performed [1]. As for the compensation for a large burn-up reactivity through 30 years, an axially movable reflector, which is located around the core, carries the major part of it and a burnable poison does the rest. This concept has achieved not only a long core lifetime but also a high discharged burn-up. On this study, a conceptual design for a small fast reactor loading U-Zr metallic fuelled core instead of U-Pu-Zr fuelled core has been conducted, based on the original core arrangement of 4S reactor [2]. Within the range of this study including safety requirements, adopting the burnable poison would be effective to construct a core concept that achieves both a long lifetime and a high discharged burn-up.

Conceptual Design Study on Fast Reactor Fuel Reprocessing System Using Super-DIREX Process

2004 ◽  
Author(s):  
Takeshi Takata ◽  
Yoshikazu Koma ◽  
Koji Sato ◽  
Takashi Shimada ◽  
Yukihide Mori ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Extraction Process ◽  
Spent Fuel ◽  
Direct Extraction ◽  
Design Study ◽  
Cycle Systems ◽  
Fast Reactor Fuel ◽  
Reprocessing Plant ◽  
Fuel Reprocessing

A conceptual design study for some alternatives as well as the advanced aqueous reprocessing system has been progressed as a feasibility study on commercialized fast reactor cycle systems. Among these alternatives, the Supercritical fluid Direct Extraction (Super-DIREX) process is expected to minimize the reprocessing cost because the heavy metals (U, Pu, Np, Am and Cm) are directly extracted from the spent fuel powder in a column covering the dissolution, clarification and extraction process of the advanced aqueous process. The conceptual design for the reprocessing plant using Super-DIREX process was conducted considering the flowsheet, mass balance, specification and number of the components and layout of the components. From the result of the evaluation for the reprocessing cost of the plant with the capacity of 50tHM/y, it is found out that about 30% of the reprocessing cost is reduced compared with the advanced aqueous process (the NEXT process). In addition, using the Super-DIREX process, about 30% of wastes generated from the plant are reduced.

Sign in / Sign up

Export Citation Format

Share Document