Systematic measurements and analyses for lead void reactivity worth in a plutonium core and two uranium cores with different enrichments

Fukushima, Masahiro; Goda, J.*; Oizumi, Akito; Bounds, J.*; Cutler, T.*; Grove, T.*; Hayes, D.*; Hutchinson, J.*; McKenzie, G.*; McSpaden, A.*; et al.

Nuclear Science and Engineering, 194(2), p.138 - 153, 2020/02

https://doi.org/10.1080/00295639.2019.1663089

To validate lead (Pb) nuclear cross sections, a series of integral experiments to measure lead void reactivity worth was conducted systematically in three fast spectra with different fuel compositions on the Comet critical assembly of the National Criticality Experiments Research Center. Previous experiments in a high-enriched uranium (HEU)/Pb and a low-enriched uranium (LEU)/Pb systems had been performed in 2016 and 2017, respectively. A follow-on experiment in a plutonium (Pu)/Pb system has been completed. The Pu/Pb system was constructed using lead plates and weapons grade plutonium plates that had been used in the Zero Power Physics Reactor (ZPPR) of Argonne National Laboratory until the 1990s. Furthermore, the HEU/Pb system was re-examined on the Comet critical assembly installed newly with a device that can guarantee the gap reproducibility with a higher accuracy and precision, and then the experimental data was re evaluated. Using the lead void reactivity worth measured in these three cores with different fuel compositions, the latest nuclear data libraries, JENDL 4.0 and ENDF/B VIII.0, were tested with the Monte Carlo calculation code MCNP version 6.1. As a result, the calculations by ENDF/B-VIII.0 were confirmed to agree with lead void reactivity worth measured in all the cores. It was furthermore found that the calculations by JENDL 4.0 overestimate by more than 20% for the Pu/Pb core while being in good agreements for the HEU/Pb and LEU/Pb cores.

Lead void reactivity worth in two critical assembly cores with differing uranium enrichments

Fukushima, Masahiro; Goda, J.*; Bounds, J.*; Cutler, T.*; Grove, T.*; Hutchinson, J.*; James, M.*; McKenzie, G.*; Sanchez, R.*; Oizumi, Akito; et al.

Nuclear Science and Engineering, 189, p.93 - 99, 2018/01

https://doi.org/10.1080/00295639.2017.1373520

To validate lead (Pb) nuclear cross sections, a series of integral experiments to measure lead void reactivity worths was conducted in a high-enriched uranium (HEU)/Pb system and a low enriched uranium (LEU)/Pb system using the Comet Critical Assembly at NCERC. The critical experiments were designed to provide complementary data sets having different sensitivities to scattering cross sections of lead. The larger amount of the U present in the LEU/Pb core increases the neutron importance above 1 MeV compared with the HEU/Pb core. Since removal of lead from the core shifts the neutron spectrum to the higher energy region, positive lead void reactivity worths were observed in the LEU/Pb core while negative values were observed in the HEU/Pb core. Experimental analyses for the lead void reactivity worths were performed with the Monte Carlo calculation code MCNP6.1 together with nuclear data libraries, JENDL 4.0 and ENDF/B VII.1. The calculation values were found to overestimate the experimental ones for the HEU/Pb core while being consistent for the LEU/Pb core.

The Integral experiment on beryllium with D-T neutrons for verification of tritium breeding

Verzilov, Y. M.; Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Klix, A.*; Nishitani, Takeo

Fusion Engineering and Design, 82(1), p.1 - 9, 2007/01

https://doi.org/10.1016/j.fusengdes.2005.12.007

no abstracts in English

Integral experiments for verification of tritium production on the beryllium/lithium titanate blanket mock-up with a one-breeder layer

Verzilov, Y. M.; Sato, Satoshi; Nakao, Makoto*; Ochiai, Kentaro; Wada, Masayuki*; Nishitani, Takeo

JAERI-Research 2004-015, 55 Pages, 2004/10

JAERI-Research-2004-015.pdf:3.29MB

no abstracts in English

A Study of existing experimental data and validation process for evaluated high energy nuclear data; Report of task force on integral test for JENDEL high energy file in japanese nuclear data committee

Oyama, Yukio; *; Watanabe, Yukinobu*; Kawano, Toshihiko*; Numajiri, M.*; Ueki, Kotaro*; *; Yamano, Naoki*; Kosako, Kazuaki*; *; et al.

JAERI-Review 98-020, 130 Pages, 1998/11

JAERI-Review-98-020.pdf:6.4MB

no abstracts in English

ROSA/AP600 testing; Facility modifications and initial test results

Kukita, Yutaka; Yonomoto, Taisuke; ; Nakamura, Hideo; Kumamaru, Hiroshige; Anoda, Yoshinari; T.J.Boucher*; M.G.Ortiz*; R.A.Shaw*; R.R.Schultz*

Journal of Nuclear Science and Technology, 33(3), p.259 - 265, 1996/03

https://doi.org/10.3327/jnst.33.259

no abstracts in English

Benchmark experiment

Oyama, Yukio; *

Purazuma, Kaku Yugo Gakkai-Shi, 72(1), p.83 - 90, 1996/00

http://ci.nii.ac.jp/naid/110003827398

no abstracts in English

Phase III experiments of the JAERI/USDOE collaborative program on fusion blanket neutronics - Line source and annular blanket experiments, Volume I; Experiment

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Maekawa, Fujio; Kosako, Kazuaki*; Nakamura, Tomoo; Maekawa, Hiroshi; M.Z.Youssef*; A.Kumar*; M.A.Abdou*; et al.

JAERI-M 94-015, 193 Pages, 1994/02

JAERI-M-94-015.pdf:6.62MB

no abstracts in English

JAERI/USDOE collaborative program on fusion blanket neutronics

Oyama, Yukio; Maekawa, Hiroshi;

Nippon Genshiryoku Gakkai-Shi, 36(7), p.612 - 618, 1994/00

no abstracts in English

A BWR pump suction-line 200% break test at ROSA-III program(RUN 903); Effect of prolonged recirculation pump operation

Suzuki, Mitsuhiro; Nakamura, Hideo; Yonomoto, Taisuke; Kumamaru, Hiroshige; Anoda, Yoshinari; Murata, Hideo

JAERI-M 91-103, 156 Pages, 1991/07

JAERI-M-91-103.pdf:4.59MB

no abstracts in English