Published 1980 | Version v1
Report

Status of data testing of ENDF/B-V reactor dosimetry file

Creators

  • 1. Brookhaven National Lab., Upton, NY (USA)

Description

The ENDF/B-V Reactor Dosimetry File was released August 1979, and Phase II Data Testing started. The results presented here are from Brookhaven National Laboratory only, and are considered preliminary. The tests include calculated spectrum averaged cross sections using 235U fission spectrum (Watt), 252Cf spontaneous fission spectrum (Watt and Maxwellian) and the Coupled Fast Reactor Measurement Facility (CFRMF) spectrum

Part of:
Dosimetry methods for fuels, cladding and structural materials

Additional details

Publishing Information

ISBN
92-825-1868-X
Imprint Title
Dosimetry methods for fuels, cladding and structural materials
Imprint Pagination
642 p.
Journal Page Range
p. 903-913.
Report number
EUR--6813(v.2)

Conference

Title
3. ASTM-EURATOM symposium on reactor dosimetry.
Dates
1 - 5 Oct 1979.
Place
Ispra, Italy.

Optional Information