Measurement and calculation of neutron densities in BWR high burn-up fuels

Nuclear Engineering and Design

Volumn 210, Issue 1-3, 2001, Pages 239-248

  Tayama, Ryuichi ^a   Hayashi, Katsumi ^a   Iwasaki, Ryo ^a   Sasaki, Masana ^a   Etoh, Yoshinori ^b   Sakurai, Hiroshi ^c  

^a HITACHI LTD   (Japan)

^b Nuclear Power Engineering Corp   (Japan)

^c NIPPON NUCLEAR FUEL DEVELOPMENT CO LTD   (Japan)

Author keywords

252Cf standard source; BF3 detector; Burn up range 30 60GWd tU 1; BWR spent fuels; Enrichment range 2.0 3.4 ; Neutron densities; Neutron scanning device

Indexed keywords

NEUTRONS; NUCLEAR FUELS; NUCLEAR POWER PLANTS;

NEUTRON DENSITIES;

BOILING WATER REACTORS;

EID: 0035575638     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(01)00427-7     Document Type: Article

References (10)

1. LENDL-84, the lawrence livermore national laboratory evaluated nuclear data library with ENDF-V format
2. Data format and procedures for the evaluated nuclear data file
3. Japanese evaluated nuclear data library version 3 revision-2: JENDL3.2
4. Amount of nuclides constituting PWR spent fuels
5. Libraries based on JENDL-3.2 for ORIGEN2 code: ORLIBJ32
6. Shielding experiments for evaluating a shielding safety evaluation code system to spent fuel processing facilities (5) - Measurement of the neutron intensity emitted from PWR spent fuel