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Journal Articles

High-sensitivity detection of fissile materials in a waste dram by direct interrogation of 14MeV acc neutrons

Haruyama, Mitsuo; Ara, Katsuyuki*; Takase, Misao*

Nippon Genshiryoku Gakkai-Shi, 43(4), p.397 - 404, 2001/04

 Times Cited Count:3 Percentile:70.15(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

ComparaUve analyses on nuclear charaderistics of water-cooled breeder cores

; Sato, Wakaei*;

JNC-TN9400 2000-037, 87 Pages, 2000/03

JNC-TN9400-2000-037.pdf:3.48MB

ln order to compare the nuclear characteristics of water-cooled bleeder cores with that of LMFBR, MOX fuel cell models are established for boiling and non-boiling LWR, non-boiling HWR and sodium-cooled reactor. Frst, the comarison is made between the heterogeneous cell calculation results by SRAC and those by SLAROM. The results show some differences as for neutron energy spectrum, one-grouped cross section and conversion ratio due to the different grouped cross section library (both are based on JENDL-3.2, though) used for each code, however, the difference is acceptably small for grasping the basic characteristics of the above-mentioned cores. Second, using the SLAROM code, main core parameters such as mean neutron energy, ratio of fast neutron and $$eta$$-value, are analyzed. The comparison between the cores show that softened neutron spectrum by the scattering effect of hydrogen or heavy hydrogen increase the contribution of nuclear reaction (especially for neutron capture reaction rather than fission reaction) in lower energy region comparing with LMFBR. ln order to overcome the effect, tighter lattice than LMFBR is necessary for water-cooled cores to realize the breeding of fissile nuclides. Third, effects of Pu isotopic composition on the breeding ratio are evaluated using SRAC burnup calculation. From the results, it is confirmed that degraded Pu (larger ratio of Pu-240) show the larger breeding ratio. At last, sensitivity analyses are made for k-effective and main reaction ratios. As for k-effective, using a temporary covariance data of JENDL-3.2, uncertainty resulting from the cross sections' error is analyzed for a boiling LWR and a sodium-cooled reactor. The boiling LWR core shows larger sensitivity in lower energy region than the sodium-cooled reactor (especially for the energy region lower than 1kev), And, 18-group analysis that is considered acceptably good for LMFBR analysis, should not be enough for accurate sensitivity estimation of ...

Journal Articles

New detection method of trace amount of fissile material in the waste drum

Haruyama, Mitsuo

Genshiryoku eye, 45(11), p.77 - 79, 1999/11

no abstracts in English

Journal Articles

Fusion development and tritium control

Konishi, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 74(8), p.808 - 810, 1998/08

no abstracts in English

JAEA Reports

Study on minor actinide transmutation in a fast reactor; Summary of core study

PNC-TN9410 93-226, 109 Pages, 1993/10

PNC-TN9410-93-226.pdf:14.44MB

Feasibility studies of minor actinide(MA) transmutation in a fast reactor have been performed to achieve the following objectives : (1)Development of a fast reactor core concept loaded with MA fuel which has no serious penalties to core performance in consideration of fuel cycle technology, (2)Conception of an innovative core by utilizing the predominant properties of MA. This paper is summarized the results of the two feasibility studies of MA transmutation in a fast reactor in PNC.

Journal Articles

Nondestructive detection method of trace amount of fissile materials by using a neutron generator

Haruyama, Mitsuo; Goto, Hiroshi; ; *

KEK-PROC-91-5, p.125 - 135, 1991/07

no abstracts in English

JAEA Reports

None

Nomura, Kazunori; ; *; *;

PNC-TN8410 91-180, 51 Pages, 1991/06

PNC-TN8410-91-180.pdf:1.06MB

None

JAEA Reports

Experimental Study on Equilibrium Partition Coefficient of Volatile Fission Products between Liquid Sodium and the Gas Phase

; ; ; ;

PNC-TN9410 91-091, 13 Pages, 1991/01

PNC-TN9410-91-091.pdf:0.31MB

A series of tests has been conducted to obtain gas-liquid equilibrium partition coefficient Kd of volatile fission products such as cesium,iodine,and tellurium in sodium. In the test a sodium pool mixed with an FP simulant was heated by an electric furnace and the solvent of trapped vapors by filters was quantitatively analyzed. The results are,(1)Cs shows the highest Kd (20-100), (2)Kd of iodine scatters as wide as 0.02-0.5at 450$$^{circ}C$$and 0.3-0.8 at 650$$^{circ}C$$,(3)the Kd values of Cs and I agree well with the theoretical ones reported by Castleman et al., and (4)if a sodium-telluride which is hard to vaporize than pure Te is assumed, measured Kd of Te agrees with that theoretical.

Journal Articles

Nondestructive detection of trace amounts of fissile material using neutrons generated by an accelerator

Haruyama, Mitsuo; Goto, Hiroshi; ; *

Hoshasen Kenshutsuki To Doshimetori, p.38 - 40, 1991/00

no abstracts in English

Journal Articles

Detection of trace amounts of spontaneously fissioning nuclides by measuring time intervals between detection pulses

Goto, Hiroshi; Haruyama, Mitsuo; ; *

Hoshasen Kenshutsuki To Doshimetori, p.41 - 43, 1991/00

no abstracts in English

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