Published May 1996 | Version v1
Journal article Metadata-only

Determination of tritium content in reactor decommissioning waste

Creators

  • 1. Ministry of Nuclear Industry, Taiyuan, SX (China). Inst. of Radiation Protection

Description

A determination method of tritium content in solid material samples such as stainless steel, carbon steel rust, scrap aluminium alloy and scale and sediment deposit in storage water pool is studied experimentally by wet-outgassing at high temperature, catalyst oxidation and bubbles collection, the parameters involved in this method and the detainees of measurement results are discussed

Additional details

Publishing Information

Journal Title
Radiation Protection (Taiyuan)
Journal Volume
16
Journal Issue
3
Journal Page Range
p. 203-208, 240.
ISSN
1000-8187
CODEN
FUFAEM

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
27068965
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
DECOMMISSIONING; DECONTAMINATION; EXPERIMENTAL DATA; RADIATION MONITORING; RADIOACTIVE WASTES; REACTORS; TRITIUM
Descriptors DEC
BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLEANING; DATA; HYDROGEN ISOTOPES; INFORMATION; ISOTOPES; LIGHT NUCLEI; MATERIALS; MONITORING; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; RADIOACTIVE MATERIALS; RADIOISOTOPES; WASTES; YEARS LIVING RADIOISOTOPES