Published October 1964 | Version v1
Book

Canadian reactor shielding

Creators

Description

It has been the policy in Canada to build radiation measuring facilities into reactor bulk shields when the reactors are under construction. Radiation attenuation through the NRX shield was measured by means of a special plug. These measurements formed the basis for the design of the NRU and NPD shields. Design calculations and measurements on the NRU shield have been published. The most recent shield measurements were carried out on NPD. Calculation of the radiation fields through the NPD shield is being carried out using removal-age-diffusion theory. Both MAC and a series of programmes written at AECL [6] are being used in this work. Preliminary calculations indicate that while agreement between calculated and measured gamma radiation and fast neutron flux is good, there is lack of agreement in the case of the thermal neutron flux. This work is continuing

Part of:
Reactor shielding. Report of a panel

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (Austria)
Imprint Title
Reactor shielding. Report of a panel
Imprint Pagination
171 p.
Journal Issue
no. 34
Series
Technical reports series
Journal Page Range
p. 3-13

Conference

Title
Panel on reactor shielding
Dates
9-13 Mar 1964
Place
Vienna (Austria)

Optional Information

Notes
6 refs, 10 figs
Secondary number(s)
STI/DOC--10/34