Published 1981 | Version v1
Book

A simple comparison of adjusted data sets for iron based on measuremets in ASPIS and in the cores of fast reactor criticals

Creators

  • 1. Imperial Coll. of Science and Technology, London (UK)

Description

The object of this comparison is to determine whether the adjustement sets for iron obtained in one case from integral measurements in ASPIS fission source and in another case from the cores of fast reactor criticals produce the same effect when used in calculations. The reasons that they may produce different effects are: (a) the adjustements may reflect shortcomings in the way integral quantities are calculated from data, for example approximations in transport theory or group averaging errors, rather than errors in nuclear data; (b) the quantities measured in ASPIS and the cores of fast reactor criticals have different sensitivities to iron cross-sections so the adjustements may be complementary rather than equivalent, for example they may span different energy ranges; (c) the standard deviations assumed for the differential data may be unrealistic. Again this will give rise to adjustements which do not reflect real errors in nuclear data

Part of:
Proceedings of a specialists' meeting on nuclear data and benchmarks for reactor shielding

Additional details

Publishing Information

Publisher
OECD.
Imprint Place
Paris, France
ISBN
92-64-2118-3
Imprint Title
Proceedings of specialist's meeting on nuclear data and benchmarks for reactor shielding, Paris, 27-29 October 1980
Imprint Pagination
432 p.
Journal Page Range
p. 79-87.

Conference

Title
Specialist's meeting on nuclear data and benchmarks for reactor shielding.
Dates
27 - 29 Oct 1980.
Place
Paris, France.

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
12619372
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPARATIVE EVALUATIONS; CROSS SECTIONS; EVALUATED DATA; IRON; MULTIGROUP THEORY; REACTOR MATERIALS; SHIELDING
Descriptors DEC
DATA; ELEMENTS; INFORMATION; METALS; NUMERICAL DATA; TRANSITION ELEMENTS; TRANSPORT THEORY

Optional Information