J 2022

Calculation and measurement of Al prompt capture gammas above water in a pool-type reactor

CZAKOJ, Tomáš; Michal KOŠŤÁL; Evžen LOSA; Zdeněk MATĚJ; Jan ŠIMON et. al.

Basic information

Original name

Calculation and measurement of Al prompt capture gammas above water in a pool-type reactor

Authors

CZAKOJ, Tomáš (guarantor); Michal KOŠŤÁL (203 Czech Republic); Evžen LOSA; Zdeněk MATĚJ ORCID (203 Czech Republic, belonging to the institution); Jan ŠIMON; Filip MRAVEC (203 Czech Republic, belonging to the institution) and František CVACHOVEC (203 Czech Republic)

Edition

NUCLEAR ENGINEERING AND TECHNOLOGY, SOUTH KOREA, KOREAN NUCLEAR SOC, 2022, 1738-5733

Other information

Language

English

Type of outcome

Article in a journal

Field of Study

10300 1.3 Physical sciences

Country of publisher

Republic of Korea

Confidentiality degree

is not subject to a state or trade secret

References:

Impact factor

Impact factor: 2.700

RIV identification code

RIV/00216224:14330/22:00128971

Organization unit

Faculty of Informatics

UT WoS

000869040500009

EID Scopus

2-s2.0-85131438730

Keywords in English

PGNAA; Reactor; Radiation heating. Prompt gamma; mcnp
Changed: 5/4/2023 04:37, RNDr. Pavel Šmerk, Ph.D.

Abstract

In the original language

Prompt capture gammas are an important part of the fission reactor gamma field. Because some of the structural materials after neutron capture can emit photons with high energies forming the dominant component of the gamma spectrum in the high energy region, the following study of the high energy capture gamma was carried out. High energy gamma radiation may play a major role in areas of the radiation sciences as reactor dosimetry. The HPGe measurements and calculations of the high-energy aluminum capture gamma were performed at two moderator levels in the VR-1 pool-type reactor. The result comparison for nominal levels was within two sigma uncertainties for the major 7.724 MeV peak. A larger discrepancy of 60% was found for the 7.693 MeV peak. The spectra were also measured using a stilbene detector, and a good agreement between HPGe and stilbene was observed. This confirms the validity of stilbene measurements of gamma flux. Additionally, agreement of the wide peak measurement in 7–9.2 MeV by stilbene detector shows the possibility of using the organic scintillators as an independent power monitor. This fact is valid in these reactor types because power is proportional to the thermal neutron flux, which is also proportional to the production of capture gammas forming the wide peak.