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JAEA Reports

Measurement of fast neutron induced fission cross section of minor-actinide

JNC TJ9400 2000-013, 47 Pages, 2000/06

JNC-TJ9400-2000-013.pdf:0.81MB

In fuel cycles with recycled actinide, core characteristics are largely influenced by minor actinide (MA:Np, Am, Cm). Accurate nuclear data of MA such as fission cross section are required to estimate the effect of MA wich high accuracy. In this study, fast neutron induced fission cross section of MA is measured using Dynamitron accelerator in Tohoku University, The followings were performed in this fiscal year; (1)Research of nuclear data of MA, (2)Sample preparation and sample mass assay, (3)Investigation of neutron sources with the energy of several 10 keV, (4)Preliminary measurement of fission cross section using Dynamitron accelerator. As the result, four $^{237}$ Np samples were prepared and the sample mass were measured using alpha-spectrometry with the accuracy of 1.2%. Then, it was confirmed that a neutron source via $^{7}$ Li(p, n) $^{7}$ Be reaction using a Li-thick target is suitable for measuring fission cross section of MA in the energy region of several 10 keV. Furthermore, it was verified by the preliminary measurement that the measurement of fission cross section of MA is available using a fission chamber and electronics developed in this study.

JAEA Reports

Measurement of fast neutron induced fission cross section of Americium isotopes

JNC TJ9400 99-007, 74 Pages, 1999/03

JNC-TJ9400-99-007.pdf:1.5MB

In a fuel cycle with recycled actinide, americium isotopes largely influence core characteristics for a fast reactor. Accurate nuclear data for americium isotopes such as fission cross section are required to estimate effect of those isotopes on a fast reactor core. Nevertheless, experimental data for those isotopes are not enough to evaluate them accurately at the present time. Under these circumstances, fast neutron induced fission cross sections of those isotopes have been measured using Dynamitron Accelerator of Tohoku University. In the present study, fission cross section ratios of Am241/Np237 and Am243/Np237 were measured at 4.0 MeV and 6.3 MeV using the improved tools and samples, which have previously developed in this study, The measured results for the fission cross sections of Am241 and Am243 at the two energy points did not agree with those in a nuclear data library, and different nuclear data libraries werc supported by the present results dependent on energy and isotope.

Journal Articles

First ISTC/SAC seminar ``New approaches to the nuclear fuel cycles and related disposal schemes; Taking into account the existing excessive quantities of weapon-grade U and Pu, and reactor-grade Pu''

Maekawa, Hiroshi; Mukaiyama, Takehiko; Yamane, Tsuyoshi; *; *; Suzuki, Atsuyuki*; Takeda, Renzo*; *; Kawashima, Masatoshi*; *; et al.

Nihon Genshiryoku Gakkai-Shi, 40(12), p.963 - 965, 1998/12

no abstracts in English

Journal Articles

Measurement and theoretical analysis of neutron elastic scattering and inelastic reactions leading to a three-body final state for $^{6}$ Li at 10 to 20 MeV

Chiba, Satoshi; *; *; *; Matsuyama, Shigeo*; Shibata, Keiichi; Iwamoto, Osamu; A.J.Koning*; G.M.Hale*; M.B.Chadwick*; et al.

Physical Review C, 58(4), p.2205 - 2216, 1998/10

https://doi.org/10.1103/PhysRevC.58.2205

Times Cited Count：16 Percentile：65.84(Physics, Nuclear)

no abstracts in English

JAEA Reports

None

*; ; *;

PNC TY9601 98-002, 69 Pages, 1998/03

PNC-TY9601-98-002.pdf:4.06MB

no abstracts in English

JAEA Reports

Measurement of fast neutron induced fission cross section of minor-actinide

PNC TJ9601 98-002, 115 Pages, 1998/03

PNC-TJ9601-98-002.pdf:2.57MB

In fuel cycles with recycled actinide, core characteristics are largely influenced by minor actinide (MA: Np, Am), Accurate nuclear data of MA such as fission cross section are required to estimate the effect of MA with high accuracy. In this study, fast neutron induced fission cross section of MA was measured using Dynamitron Accelerator in Tohoku University. New or improved techniques and tools with high precision and fast timing capability were developed for this study. Those are as follows: (1)Development of a sealed fission chamber,(2)Intensification of Li neutron target, (3)Improvement of time-resolution of Time-of-Right (TOF) electronic circuit, (4)Introduction of MA (Np237, Am241 and Am243) samples with large sample mass and (5)Introduction of a U235 sample with high purity. Using these improved tools and samples, fission cross section of Np237 was measured between 10 to 100 keV. On the other hand, averaged fission cross section for Maxwell distribution spectrum with kt=25.3 keV was measured for Am241 and Am243.

JAEA Reports

Integrated burnup calculation code system SWAT

Suyama, Kenya; *; *

JAERI-Data/Code 97-047, 128 Pages, 1997/11

JAERI-Data-Code-97-047.pdf:3.06MB

no abstracts in English

JAEA Reports

None

*; ; *;

PNC TY9601 97-001, 113 Pages, 1997/03

PNC-TY9601-97-001.pdf:3.37MB

no abstracts in English

JAEA Reports

Measurement of fast neutron induced fission cross section of minor-actinide

PNC TJ9601 97-001, 51 Pages, 1997/03

PNC-TJ9601-97-001.pdf:1.05MB

In fuel cycles with recycled actinide, core characteristics are largely influenced by minor actinide (MA:Np, Am, Cm). Accurate nuclear data of MA such as fission cross section are required to estimate the effect of MA with high accuracy.In this study fast neutron induced fission cross section of MA is measured using Dynamitron Accelerator in Tohoku University. The experimental method and the samples, which were developed or introduced during the last year, were improved in this fiscal year: (1)Development of a sealed fission chamber, (2)Intensification of Li neutron target, (3)Improvement of time-resolution of Time-of-flight (TOF) electronic circuit, (4)Introduction of Np237 samples with large sample mass and (5)Introduction of a U235 sample with high purity. Using these improved tools and samples, the fission cross section ratio of NP237 relative to U235 was measured between 5 to 100keV, and the fission cross section of Np237 was deduced. On the other hand, samples of Am241 and Am243 were obtained from Japan Atomic Energy Research Institute (JAERI) after investigating fission cross section of two americium isotopes (Am241 and Am243) which are important for core physics calculation of fast reactors.

JAEA Reports