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JAEA Reports

Use results of MOX fuel in ATR Fugen nuclear power station

Ijima, Takashi; ; Matsumoto, Mitsuo; *

JNC TN3410 2000-002, 93 Pages, 2000/01

JNC-TN3410-2000-002.pdf:2.54MB

Fugen Nuclear Power Station ("Fugen") is a prototype Advanced Thermal Reactor (ATR), it has been demonstrated the plutonium utilization by loading many Mixed Oxide Fuels (MOX) since the reactor start up March 1979, and no fuel defect had been occurred, The MOX fuel assemblies has the high reliability and has been loaded more than 700 fuel assemblies. This is the largest in the world as a thermal neutron reactor. However, "Fugen" is planning to stop its operation in the year 2003, because the role of the Fugen almost finished. Therefore, we are going to summarize the ATR project including the Plutonium utilization experience. This paper is summarized as part of the experience.

Journal Articles

JENDL-3 revision 2 - Its evaluation and validation

; Takano, Hideki; Nakagawa, Tsuneo

Transactions of the American Nuclear Society, 73, p.424 - 425, 1995/00

no abstracts in English

Journal Articles

Int.Topical Mtg.on Safety of Thermal Reactor

Soda, Kunihisa

Nihon Genshiryoku Gakkai-Shi, 33(10), p.950 - 951, 1991/10

no abstracts in English

JAEA Reports

In-pile Test of Tririum Release from Lithium Oxide; An Evalution Study on Neutronics and Thermohydraulics of Sweep Gas Capsule Packed with Li$$_{2}$$O Pellets

Kurasawa, T.; ; ; ; ; ; ; ; ;

JAERI-M 84-013, 47 Pages, 1984/02

JAERI-M-84-013.pdf:1.44MB

no abstracts in English

Journal Articles

Report on the second version of Japanese evaluated nuclear data library JENDL-2

Igarashi, Shinichi; Asami, Tetsuo; Kikuchi, Yasuyuki; Nakagawa, Tsuneo; Narita, Tsutomu; Shibata, Keiichi

Nihon Genshiryoku Gakkai-Shi, 26(3), p.191 - 198, 1984/00

https://doi.org/10.3327/jaesj.26.191
 Times Cited Count：3 Percentile：38.12(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Thermal Reactor Benchmark Tests on JENDL-2

; ; ; Akino, Fujiyoshi; ; *

JAERI-M 83-202, 41 Pages, 1983/11

JAERI-M-83-202.pdf:1.14MB

no abstracts in English

JAEA Reports

TIMS-PGG:A Code System for Producing Group Constant in Fast Neutoron Energy Region

; ; *

JAERI-M 82-072, 105 Pages, 1982/07

JAERI-M-82-072.pdf:2.34MB

no abstracts in English

JAEA Reports

Critical Experiment for Power Flattening in Plutonium Fuel Lattice, 1; Measurement of Power Distribution

Murakami, Kiyonobu; ; ; Ono, Akio*; ; *; *; *

JAERI-M 9876, 83 Pages, 1982/01

JAERI-M-9876.pdf:3.09MB

no abstracts in English

Journal Articles

Build-up and decay of actinide nuclides in fuel cycle of nuclear reactors

Tasaka, Kanji; Kikuchi, Yasuyuki; ;

Journal of Nuclear Science and Technology, 14(7), p.519 - 531, 1977/07

https://doi.org/10.3327/jnst.14.519
 Times Cited Count：1

no abstracts in English

JAEA Reports

Calculations on Neutron Irradiation Damage in Reactor Materials

; Shiraishi, K.

JAERI-M 6358, 40 Pages, 1976/01

JAERI-M-6358.pdf:1.17MB

no abstracts in English

JAEA Reports

Experiments and Calculations on $$beta$$$$_{e}$$$$_{f}$$$$_{f}$$/l for the Two Regional Cores of Light Water Moderated UO$$_{2}$$ and PuO$$_{2}$$-UO$$_{2}$$ Lattices

; *

JAERI-M 4696, 56 Pages, 1972/02

JAERI-M-4696.pdf:1.64MB

no abstracts in English

Journal Articles

Pu in thermal neutron reactors and fast reactors

Nihon Genshiryoku Gakkai-Shi, 4(12), 878 Pages, 1962/00

https://doi.org/10.3327/jaesj.4.878

no abstracts in English

Journal Articles

Research on the dynamic characteristics of thermal neutron reactors

;

Genshiryoku Hatsuden, 3(2), P. 69, 1959/00

https://ci.nii.ac.jp/naid/40017726036

no abstracts in English

Journal Articles

Research on the dynamical characteristics of thermal neutron reactors

;

Genshiryoku Hatsuden, 3(2), P. 69, 1959/00

https://ci.nii.ac.jp/naid/40017726036

no abstracts in English

JAEA Reports

Useful Charts to Find Indicial Response of Thermal Reactors

;

JAERI 4006, 22 Pages, 1958/07

JAERI-4006.pdf:6.5MB

no abstracts in English

JAEA Reports

Numerical Tables and Charts Useful for the Study of the Dynamic Behavior of Thermal Reactors

;

JAERI 4005, 24 Pages, 1958/07

JAERI-4005.pdf:3.12MB

no abstracts in English

16 (Records 1-16 displayed on this page)
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