J 2015

Neutron and Gamma Spectrometry in the Research Reactor LR-0

ZARITSKIY, S., B. OSMERA, František CVACHOVEC, M. MARIK, S. POSTA et. al.

Základní údaje

Originální název

Neutron and Gamma Spectrometry in the Research Reactor LR-0

Autoři

ZARITSKIY, S. (643 Rusko), B. OSMERA (203 Česká republika), František CVACHOVEC (203 Česká republika), M. MARIK (203 Česká republika), S. POSTA (203 Česká republika), V. RYPAR (203 Česká republika), D. RIAZANOV (643 Rusko), V. LICHADEEV (643 Rusko), Antonín KOLROS (203 Česká republika) a Zdeněk MATĚJ (203 Česká republika, domácí)

Vydání

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, PISCATAWAY, IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC, 2015, 0018-9499

Další údaje

Jazyk

angličtina

Typ výsledku

Článek v odborném periodiku

Obor

20305 Nuclear related engineering; ;

Stát vydavatele

Spojené státy

Utajení

není předmětem státního či obchodního tajemství

Impakt faktor

Impact factor: 1.198

Kód RIV

RIV/00216224:14330/15:00087422

Organizační jednotka

Fakulta informatiky

UT WoS

000356459900002

Klíčová slova anglicky

He-3 chamber; activation method; LR-0 reactor; neutron and gamma spectra; power distribution; power monitoring; spectrometry; stilbene; VVER mock-up
Změněno: 19. 5. 2017 11:45, RNDr. Pavel Šmerk, Ph.D.

Anotace

V originále

The complex measurement system for the full-scale VVER models (mock-ups), created in the research reactor LR-0, is discussed. Fast neutron (energy from 0.5 to 10 MeV) and gamma spectra are measured in several representative points of the mock-ups by the two-parameter spectrometer with the cylindrical stilbene scintillation detectors. Measurements in the thermal and epithermal neutron region are carried out with the activation method using a broad set of activation monitors and with the He-3(n, p) counter. Activation measurements with threshold fast neutron detectors enlarge also the proton-recoil spectra measurements, such activation measurements are carried out especially in cases, when a spectrometer cannot be put in the necessary position. The core fission rate distribution is obtained by means of gamma-scanning of the fuel pins. The low noise precise power (flux density) monitoring system, independent of the operation control system, was developed in the LR-0 reactor for mock-up experiments.