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Title: Uranium nitride fuel development, SNAP-50

Abstract

Declassified 12 Sep 1973. Development of UN in four major areas is presented: 1) powder synthesis and powder metallurgical fabrication, 2) physical and mechanical property testing, 3) fuel-cladding compatibility and barrier development, and 4) irradiation evaluation. Synthesis and sintering methods for producing large quantities of high-densily and high-purity UN are described. Results of experimental studies of the following properties are summarized: melting point, thermal conductivity, thermal expansion, vapor pressure, and thermodynamics, heat capacity, hot hardness, compressive creep, nitrogen self- diffusion, and electrical resistivity. Compatibility tests are described which demonstrated the need for a diffusion barrier. Lithium soak tests for up to 11,000 h at 2200 deg F demonstrated the stability and practicality of vapor- deposited tungsten-lined Nb--1 Zr alloy over the projected life and temperature of SNAP50. Similar static tests of purposely defected simulated fuel pins indicate a relatively high degree of stability of UN towards lithium. Instrumented capsule irradiation tests of simulated Nb--1 Zr alloy - clad fuel pins are described under 2 Mw(t) and 8 Mw(t) SNAP-50 conditions. Under 8 Mw(t) conditions, 20% fission gas release and 2% diametral cladding growth were observed after 2750 h at 2200 deg F (2.0 at.% U burnup). In-pile operation under 2more » Mw(t) conditions was achieved for 5940 h at 2000 deg F (1.0 at.% U burnup) and 3360 h at 2200 deg F (1.5 at.% U burnup) while experiencing less than 0.2% fission gas release and less than 0.4% diametral growth. (66 figures) (auth)« less

Authors:
; ;
Publication Date:
Research Org.:
Pratt and Whitney Aircraft, Middletown, Conn. (USA). Connecticut Advanced Nuclear Engineering Lab.
Sponsoring Org.:
US Atomic Energy Commission (AEC)
OSTI Identifier:
4324037
Report Number(s):
PWAC-488
NSA Number:
NSA-29-029990
DOE Contract Number:  
AT(30-1)-2789
Resource Type:
Technical Report
Resource Relation:
Other Information: Declassified 12 Sep 1973. Orig. Receipt Date: 30-JUN-74
Country of Publication:
United States
Language:
English
Subject:
N50100* -Metals, Ceramics, & Other Materials-Ceramics & Cermets; N77800 -Reactors-Space, Mobile, Propulsion, Transportation & Package Reactors; *NUCLEAR FUELS; *SNAP REACTORS- NUCLEAR FUELS; *URANIUM NITRIDES; COMPATIBILITY; FABRICATION; IRRADIATION; LITHIUM; MECHANICAL PROPERTIES; PHYSICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; NESDPS Office of Nuclear Energy Space and Defense Power Systems

Citation Formats

DeCrescente, M A, Freed, M S, and Caplow, S D. Uranium nitride fuel development, SNAP-50. United States: N. p., 1965. Web. doi:10.2172/4324037.
DeCrescente, M A, Freed, M S, & Caplow, S D. Uranium nitride fuel development, SNAP-50. United States. doi:10.2172/4324037.
DeCrescente, M A, Freed, M S, and Caplow, S D. Fri . "Uranium nitride fuel development, SNAP-50". United States. doi:10.2172/4324037. https://www.osti.gov/servlets/purl/4324037.
@article{osti_4324037,
title = {Uranium nitride fuel development, SNAP-50},
author = {DeCrescente, M A and Freed, M S and Caplow, S D},
abstractNote = {Declassified 12 Sep 1973. Development of UN in four major areas is presented: 1) powder synthesis and powder metallurgical fabrication, 2) physical and mechanical property testing, 3) fuel-cladding compatibility and barrier development, and 4) irradiation evaluation. Synthesis and sintering methods for producing large quantities of high-densily and high-purity UN are described. Results of experimental studies of the following properties are summarized: melting point, thermal conductivity, thermal expansion, vapor pressure, and thermodynamics, heat capacity, hot hardness, compressive creep, nitrogen self- diffusion, and electrical resistivity. Compatibility tests are described which demonstrated the need for a diffusion barrier. Lithium soak tests for up to 11,000 h at 2200 deg F demonstrated the stability and practicality of vapor- deposited tungsten-lined Nb--1 Zr alloy over the projected life and temperature of SNAP50. Similar static tests of purposely defected simulated fuel pins indicate a relatively high degree of stability of UN towards lithium. Instrumented capsule irradiation tests of simulated Nb--1 Zr alloy - clad fuel pins are described under 2 Mw(t) and 8 Mw(t) SNAP-50 conditions. Under 8 Mw(t) conditions, 20% fission gas release and 2% diametral cladding growth were observed after 2750 h at 2200 deg F (2.0 at.% U burnup). In-pile operation under 2 Mw(t) conditions was achieved for 5940 h at 2000 deg F (1.0 at.% U burnup) and 3360 h at 2200 deg F (1.5 at.% U burnup) while experiencing less than 0.2% fission gas release and less than 0.4% diametral growth. (66 figures) (auth)},
doi = {10.2172/4324037},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1965},
month = {10}
}