Shielding Experiments in a Liquid-Metal-Reactor Critical Assembly

Conference · Sun Sep 18 00:00:00 EDT 1988

OSTI ID:6797685

Brumbach, S. B. ^[1]; Grasseschi, G. L. ^[1]; Collins, P. J. ^[1]

---

1. Argonne National Laboratory (ANL), Argonne, IL (United States)

Results are presented for experiments in ZPPR characterizing the neutron flux and neutron spectra through prototype LMR shields. Shield compositions were (by volume) 90% stainless steel/10% sodium and 39% natural B4C/21% stainless steel/40% sodium. Measurements were made through core, blanket, reflector, shield and ex-core sodium pool regions with foils of STVU, STYU and indium and boron chambers. Proton recoil spectra were measured in the sodium pool. Core analysis methods (nodal transport, xy geometry, 21 energy groups) were used to calculate spectra and reaction rates. Agreement with measurement varied among regions, with C/E values for STVU fission larger than unity in thick steel regions and with C/E for other reactions decreasing with radius through the shield and sodium pool.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6797685
• Report Number(s): CONF-880911-31; ON: DE89005868
• Resource Relation: Journal Volume: 2; Conference: International Reactor Physics Conference, Jackson Hole, WY (United States), 18-22 Sep 1988; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
LMFBR TYPE REACTORS
SHIELDING
BORON
COMPUTER CALCULATIONS
EXPERIMENTAL DATA
INDIUM
MEASURING METHODS
NEUTRON FLUX
NEUTRON SPECTRA
REACTOR PHYSICS
SODIUM
STAINLESS STEELS
URANIUM 235
URANIUM 238
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALI METALS
ALLOYS
ALPHA DECAY RADIOISOTOPES
BREEDER REACTORS
DATA
ELEMENTS
EPITHERMAL REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FAST REACTORS
FBR TYPE REACTORS
HEAVY NUCLEI
HIGH ALLOY STEELS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LIQUID METAL COOLED REACTORS
METALS
MINUTES LIVING RADIOISOTOPES
NUCLEI
NUMERICAL DATA
PHYSICS
RADIATION FLUX
RADIOISOTOPES
REACTORS
SEMIMETALS
SPECTRA
STEELS
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
Nuclear Criticality Safety Program (NCSP)
Zero Power Physics Reactor (ZPPR) Characterizing
Prototype LMR Shields
STVU
Indium and Boron Chambers
Proton Recoil Spectra
Sodium Pool
Core Analysis Methods
210500* - Power Reactors
Breeding