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Hayashi, Takao; Tobita, Kenji; Nishio, Satoshi; Ikeda, Kazuki*; Nakamori, Yuko*; Orimo, Shinichi*; DEMO Plant Design Team
Fusion Engineering and Design, 81(8-14), p.1285 - 1290, 2006/02
Times Cited Count：22 Percentile：78.83(Nuclear Science & Technology)Neutron transport calculations were carried out to evaluate the capability of metal hydrides and borohydrides as an advanced shielding material. Some hydrides indicated considerably higher hydrogen content than polyethylene and solid hydrogen. The hydrogen-rich hydrides show superior neutron shielding capability to the conventional materials. From the temperature dependence of dissociation pressure, ZrH
and TiH can be used without releasing hydrogen at the temperature of less than 640 
C at 1 atm. ZrH and Mg(BH
) can reduce the thickness of the shield by 30% and 20% compared to a combination of steel and water, respectively. Mixing some hydrides with F82H produces considerable effects in 
-ray shielding. The neutron and -ray shielding capabilities decrease in order of ZrH 
Mg(BH) and F82H TiH and F82H water and F82H.
Iijima, Susumu*; Kato, Yuichi*; Takasaki, Kenichi*; Okajima, Shigeaki
JAERI-Data/Code 2004-016, 91 Pages, 2004/12
JAERI-Data-Code-2004-016.pdf:7.45MB
The calculation code system "EXPARAM" was designed to analyze the experimental results systematically measured at the fast critical assembly (FCA). Some calculation codes developed independently in JAERI and in US research institutes were collected and arranged as the fast reactor physics calculation code system. The multi-group core calculation code and the perturbation calculation code based on the diffusion theory and the transport theory calculate the reactor physics parameters such as eigenvalue, reaction rate, Doppler reactivity worth and sodium void worth. The dynamic physics parameters such as prompt neutron lifetime and effective delayed neutron fraction are also calculated. Input and Output data of calculation codes are transferred to each other using a direct access file on UNIX computer system.
Okumura, Keisuke
Nihon Genshiryoku Gakkai Dai-36-Kai Robutsuri Kaki Semina Tekisuto, p.81 - 102, 2004/08
The modern node method which uses a discontinuous factor has come to be widely used recently in the reactor core analyses of commercial light water reactors. The basic theory, numerical computation technique and examples of calculation results are explained for biginners of the modern nodal method.
Sato, Satoshi
JAERI-Research 2003-014, 223 Pages, 2003/09
JAERI-Research-2003-014.pdf:10.94MB
no abstracts in English
*; *; *; Seki, Yasushi
Fusion Engineering and Design, 27, p.269 - 274, 1995/00
no abstracts in English
Oyama, Yukio; Maekawa, Hiroshi;
Nihon Genshiryoku Gakkai-Shi, 36(7), p.612 - 618, 1994/00
no abstracts in English
Annals of Nuclear Energy, 18(8), p.455 - 465, 1991/00
Times Cited Count：3 Percentile：40.8(Nuclear Science & Technology)no abstracts in English
; Kawamura, Hiroshi; ;
JAERI-M 87-036, 51 Pages, 1987/03
no abstracts in English
*; *; ; *; *
JAERI-M 86-084, 32 Pages, 1986/06
no abstracts in English
Nakagawa, Masayuki; ; *; M.Z.Youssef*; J.Jung*; M.E.Sawan*
JAERI-M 85-201, 281 Pages, 1985/12
no abstracts in English
; *; ; ; ;
JAERI-M 83-061, 33 Pages, 1983/04
no abstracts in English
; ; ; ; *; *
JAERI 1285, 242 Pages, 1983/01
no abstracts in English
;
Journal of Nuclear Science and Technology, 17(4), p.301 - 304, 1980/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
*; *; *; ;
JAERI-M 8247, 89 Pages, 1979/05
no abstracts in English
; ; *
JAERI-M 6783, 69 Pages, 1976/11
no abstracts in English
