A Proposal of benchmark calculation on reactor physics for metallic fueled and MOX fueled LMFBR based upon mock-up experiment at FCA

Oigawa, Hiroyuki; Iijima, Susumu; Sakurai, Takeshi; Okajima, Shigeaki; Ando, Masaki; Nemoto, Tatsuo; Kato, Yuichi*; Osugi, Toshitaka

Journal of Nuclear Science and Technology, 37(2), p.186 - 201, 2000/02

https://doi.org/10.3327/jnst.37.186

no abstracts in English

Development of a standard data base for FBR core nuclear design(II); JUPITER-I experlmental data book

*

PNC TN9410 93-010, 502 Pages, 1992/12

PNC-TN9410-93-010.pdf:17.39MB

The present report compiles the experimental data of JUPITER phase-I, which was a joint research program between U.S.DOE and PNC of Japan, using the ZPPR facility at ANL-Idaho in 1978 to 1979. The JUPITER-I experiment was a series of critical experiments for conventional two-zone homogeneous cores of 600 to 800 MWe-class LMFBR, including seven experimental cores The nuclear characteristics recorded here include criticality, control rod reactivity, reaction rate distribution, sodium void reactivity, sample reactivity, Doppler reactivity, gamma heating and neutron spectrum. (1)ZPPR-9 : two-region cylindrical clean core with volume of app. 4,600 liters, (2)ZPPR-10A : hexagonal engineering-mockup core with 19 cotrol-rod positions(CRPs), (3)ZPPR-10B : changes seven CRPs to control rods(CRs) from ZPPR-10A, (4)ZPPR-10C : volume of app. 6,200 liters with similar core arrangement to ZPPR-10A, (5)ZPPR-10D : 31 CRPs with the same volume as ZPPR-10C, (6)ZPPR-10D/1 : changes the central CRP to a CR from ZPPR-10D, and, (7)ZPPR-10D/2 : changes seven CRPs to CRs from ZPPR-10D. The present work is a part of efforts to develop a standard data base for LMFBR core nuclear design at PNC. The detail of experimental data is thoroughly recorded here so as to re-analyze these experiments in future. In addition, these experimental data are installed in the computer system at OEC for convenience of analytical code input.